IR 05000338/2008301: Difference between revisions

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{{Adams
{{Adams
| number = ML082390072
| number = ML082390032
| issue date = 08/22/2008
| issue date = 08/22/2008
| title = June 2008 Exam 05000338/2008301 & 05000339/2008301 - Administrative Documents
| title = Exam 05000338/2008301 - Final Outlines
| author name =  
| author name =  
| author affiliation = - No Known Affiliation
| author affiliation = NRC/RGN-II
| addressee name =  
| addressee name =  
| addressee affiliation = NRC/RGN-II
| addressee affiliation =  
| docket = 05000338, 05000339
| docket = 05000338, 05000339
| license number =  
| license number =  
Line 12: Line 12:
| case reference number = 50-338/08-301, 50-339/08-301
| case reference number = 50-338/08-301, 50-339/08-301
| document type = License-Operator, Part 55 Examination Related Material
| document type = License-Operator, Part 55 Examination Related Material
| page count = 61
| page count = 13
}}
}}


Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:ADMINISTRATIVE DOCUMENTS (Yellow Paper)1.Exam Preparation ChecklistES-201-1.//'ES-301-5 Control Room Systems&Facility Walk-Thru Test Outline
{{#Wiki_filter:Final Submittal (Blue Paper)
.Operating Test Quality Check Sheet.Simulator Scenario Quality Check Sheet.Transient and Event Checklist.Exam Outline Quality Checklist.........................
FINAL OUTLINES NORTH ANNA JUNE 2008 EXAM 05000338/2008301 & 05000339/2008301
..ES-201-2./Exam Security Agreement(s)ES-201-3/Administrative Topics Outline ES-301-1//ES-301-2.ES-301-3//ES-301-4 8.2.6.7.5.3.4.9.Competencies Checklist 1J!A:-ES-301-6/10.Written Exam Quality Check Sheet, ES-401-6/'11.Written Exam Review Worksheet m:.......................
..ES-401-9/12.Written Exam Grading Quality
, ES-403-1/13.Post-Exam Check SheetES-501-1..,/14.Facility Submittal LetterDrJ:)0-/2-08[t/NORTH ANNA JUNE 2008 EXAM 05000338/2008301
&05000339/2008301  
:
Preparation Checklist Form ES*201*1 Ar.V\rAog Facility: Date of Examination:JL.l\.ie Developed by:
NRCD II OperatingNRC 0 Target Chief Date*Task Description (Reference)
Examiner's Initials-180 1.Examination administration date confirmed (C.1.a;9.2.a and b)1tU-
-120 2.NRC examiners and facility contact assigned (C.1.d;C.2.e)
-120 3.Facility contact briefed on security and other requirements (C.2.c)
-120 4.Corporate notification letter sent (C.2.d)
;Jif[
[-90][5.Reference material due (C.1.e;C.3.c;Attachment 3)]3/i>>{-75}6.Integrated examination outline(s)
due, including FormsES-201-2,ES-201-3, ES-301-1,ES-301-2,ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and IlIt- as applicable (C.1.e and f;C.3.d){-70}{7.


outline(s)
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
reviewed by NRC and feedback provided to facility tftIv licensee C.3.e)}I 1>fP-(?()-
      *3 * Total 18 3 3 6 Emergency &
{-45}8.*ropose-afninations (including writ walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3,ES-301-4,ES-301-5, ES-301-6, and ES-401-6, and any Form'PJJ!L ES-201-3 updates), and reference materials due (C.1.e, f, g and h;C.3.d)
Abnormal 2 0 ;J ;; NlA :2 NlA I 9 :2 ~ 4 Plant        ,...
-30 9.Preliminary license applications (NRC Form 398's)due (C.1.1;C.2.g;1!J(ES-202)-14 10.Final license due and Form ES-201-4 prepared (C.1.1;C.2.i;ES-202).<:;'-14 11.Examination approved by NRC supervisor for facility licensee review./'1PJt v14S (C.2.h;C.3.f)-14 12.Examinations reviewed with facility licensee (C.1.j;C.2.f and h;
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 \ ~
-1M--7 13.Written examinations and operating tests approved by NRC supervisor"KIP (C.2.i;C.3.h)-7 14.Final applications reviewed;1 or 2 (if>10)applications audited to confirm qualifications
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)
/eligibility; and examination approval and waiver letters sent flU(C.2.i;Attachment 5;ES-202, C.2.e;ES-204)-7 15.Proctoring/written exam administration guidelines reviewed tfv ,{fb with facility licensee (C.3.k)-7 16.Approved scenarios, job performance measures, and questionsdistributed to NRC examiners (C.3.i)*Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter.They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.[Applies only]{Does not apply}to examinations prepared by the NRC.
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


ES-201 Facility: North Anna Item Examination Outline Quality Checklist Date of Exam ination: 6/2/08-6/6/08&6/16/08-6/20108 Task Description Initials a b*c#1.W R I T T E N 2.S I M U L A T o R 3.W I T 4.G E N E R A L a.Verify that the outline(s)
ES401    2 ES-401    PWR ExIImlnaIIon 0IItIIne  Fonn~1*2 and .Abnomlal PI8nt EvolutIon** TIer 1JGnluD 1 IRQ I SRO\
fit(s)the appropriate model, in accordance with ES-401.b.Assess whether the outline was systematically and randomly prepared in accordance with Section D.1 of ES-401 and whether all KIA categories are appropriately sampled.c.Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.d.Assess whether the justifications for deselected or rejected KIA statements are appropriate.


a.Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, and major transients.
    '. .. 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."


b.Assess whether there are enough scenario sets (and spares)to test the projected number and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants'
~
audit test(s), and that scenarios will not be repeated on subsequent days.c.To the extent possible, assess whether the outline(s)
(, 000022 loA of Rx Coolant Makeuo / 2  P-. O;l.~ A '11-1. ~3.\
conform(s)
- 7 000025 loA of RHR SVIlWIl/4 ll. S ~ c,~jlA '."3 O;Jr-Atl ,.\:,
with the qualitative and quantitative criteria specified on Form ES-301-4 and described in Appendix D.a.Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2: (1)the outline(s)
        (.'iJ:S") ~:J*8 n.(g Po S S C'JIIAr;,~. I. ') ('11.5) S'I.?
contain(s)
- I 000028 loA of CClnlpoMnt COOlIng Watat/8    p-. o;lll AA J. 01  ~ q 000027 Preuurtzer P,..". Ccntrof
the required number of control room and in-plant tasks distributed among the safety functions as specified on the form (2)task repetition from the last two NRC examinations is within the limits specified on the form (3)no tasks are duplicated from the applicants'
      ~ r.. 0,1'1 A(,,2.;2. 'i fP~
audit test(s)(4)the number of new or modified tasks meets or exceeds the minimums specified on the form (5)the number of alternate path, low-power, emergency, and RCA tasks meet the criteria on the form.b.Verify that the administrative outline meets the criteria specified on Form ES-301-1: (1)the tasks are distributed among the topics as specified on the form (2)at least one task is new or significantly modified (3)no more than one task is repeated from the last two NRC licensing examinations c.Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.a.Assess whether plant-specific priorities (including PRA and IPE insights)are covered in the appropriate exam sections.b.Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
SYIltem MeIfunc:Uon / 3
    ['r  {l.. O;lq El<..I.OS'  Il ATWS /1 (j) oo38 Steam Gen. Tube RUDCUnt I 3
    .$ ~ 03?,.&#xa3; 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 &#xa3; /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


c.Ensure that KIA importance ratings (except for plant-specific priorities)
( ES-401    3    Form ES"1-2 ES-401    PWR ea... .ac.. 0utIne    Fonn es..401~
are at least 2.5.d.Check for duplication and overlap among exam sections.e.Check the entire exam for balance of coverage.f.Assess whether the exam fits the appropriate job level (RO or SRO).N-I{\/-I fJ-11JK v Note:#Independent NRC reviewer initial items in Column"c";chief examiner concurrence required.*Not applicable for NRC-prepared examination outlines ES-201 Examination Outline Quality Checklist oPl7L('}\)!Jf::, fC-S T-'dlt(.{.,\f Facility: North Anna Date of Exam ination: 6/2/08-6/6/08&6/16/08-6/20/08 Initials Item Task Description a b*c#1.a.Verify that the outline(s)
8nd Abnclrm8l Pl8nt EvalUIIanI- 11er 1/Grnun 2 IRQ J SRO)
fit(s)theappropriate model, in accordance with ES-401.'fA%W R b.Assess whether the outline was systematically and randomly prepared in accordance with rJfr fr Section D.1 of ES-401 and whether all KIA categories are appropriately sampled.TT c.Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.E NIA%N d.Assess whether the justifications for deselected or rejected KJA statements are appropriate.
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."


2.a.Using Form that the proposed scenario sets cover the required number1iU-of normal evolutions, instrument and component failures, technical specifications, 1M>S and major transients.
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


I M b.Assess whether there are enough scenario sets (and spares)to test the projected number JilL U and mix of applicants in accordance with the expected crew composition and rotation schedule df L without compromising exam integrity, and ensure that each applicant can be tested using lu'1 A at least one new or significantly modified scenario, that no scenarios are duplicatedTfromthe applicants'
ES-401    . Fonn ES-401*2 \
audit test(s), and that scenarios will not be repeated on subsequent days.0 To the extent possible, assess whether the outline(s)
I E5-401 I ~
conform(s)
    , ~ 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 #
with the qualitative IJf 1M-R c.tv')and quantitative criteria specified on Form ES-301 described in Appendix D.N'&3.a.Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2: (1)the outline(s)
1 2 3 4 5 8 1 2 3  4
contain(s)
,     fZ ~ o03A~. 0'1 R.2** ~
the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form.,,-/(2)task repetition from the last two NRC examinations is within the limits specified on the form"",.T (3)no tasks are duplicated from the applicants'
003 Reactor CooI8nt PumD R ~ oO"\G1,l. ~U
audit test(s)/au-(4)the number of new or modified tasks meets or exceeds the minimums specified on the form/" (5)the number of alternate path, low-power, emergency, and RCA tasks meet the rttJ on the form.b.Verify that the administrative outline meets the criteria specified on Form ES-301-1: 'J (1)the tasks are distributed among the topics as specified on the form V-L-j 1jU.(2)at least one task is new or significantly modifiedlv (3)no more than one task is repeated from the last two NRC licensing examinations
%. 004 ChemIcal 80d VoIwne Control
...-c.Determine if there are enough different outlines to test the projected number and mix fP-of applicants and ensure that no items are duplicated on subsequent days.'-/4.a.Assess whether plant-specific priorities (including PRA and IPE insights)are covered:....-6\r0$K-in the appropriate exam sections.f{'C>G c-i I.\E b.Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate.
- J f(   S> I~ 005G,t*.1.,,\P('1).l.('1J.5)  5 ".7 005 ReIIdu8I Hut Remov8I    00< \l. \. o<P  /1.3.s"
'4  Core CooIlna IR  .s I ~ 00t, A.1.0~k-)
DOIs> '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 &#xa5;. '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~ &#xa5;..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


N V'IEnsure that KiA importance ratings (except for plant-specific priorities)
~~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\
are at least 2.5.1:_:1 IliA E c.v vR d.Check for duplication and overlap among exam sections.AiwL e.Check the entire exam for balance of coverage.1/f.Assess whether the exam fits the appropriate job level (RO or SRO).-('-.tl"'J:t\'1'"17\'
System til Nine
Name/Signature
    * t
.\I a.Author(,(i/'17.-'.,l_\5 (L\\.\--.-.
    ,. of , " 7 >"
b.Facility Reviewer (*)
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
c.NRC Chief Examiner (#)
'.
11.RA'T&#xa3;5I1YJIJiJ. L.enRAUifflD..
,
d.NRC Supervisor UPJA:iet4..LT,\I nf)A D..J;Al/
001 Control Rod DrIve
1 I-tJrf;oitJi
      "R R 0'1 ~,lf.?1  1t'l, l 002 Re8dor CoolInt
/(9\-Note:#Independent NRC reviewer initial items in Column"c";chief examiner concurrence re,quired.
} 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


.....Not applicable for NRC-prepared examination outlines Memorandum July 11, 2008 To: Mr.Mark Bates US NRC Sam Nunn Atlanta Federal Building 61 Forsythe St., S.W>Suite 23T85 Atlanta, Georgia 30303-8931 From: Walt Shura Dominion (North Anna Power Station)1022 Haley Drive Mineral, Virginia 2311 7 Return of ES-201-3 Examination Security Agreement Forms
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


==Dear Mark,==
ESw401  Record of ReJl::ect=ed::..:.::KI:.:;AI=-  ...;.F..::o~nn~E;;;;S;...-40;.;;..;.1-i_
Enclosed please find page 1-3 ofES-201-3 Examination Security Forms.All signatures needed have been obtained.I might mention that page 3 contains both copied and original signatures.
rterl Randomly    Reason for Rejection Group selected KIA T1../<r1 011 EK \.0\
  &#xa5;.IA
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            {.
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I could get page 3 resigned if required.Please advise.I want to thank you and Bruno for your assistance in preparing the exam.Obviously, the results are not what ether of us wanted or expected, but that's not for the lack of trying.We will go forward with our root cause at North Anna and apply the lessons learned to our next exam.Where possible, we will attempt to effect changes in the process-both from a utility and a regulatory perspective.
* 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.&#xa3;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'


Perhaps we will meet in Atlanta during the upcoming workshop on examination development.
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).


Sincerely, Walt Shura Supervisor Nuclear Training North Anna Power Station
(ALL) (G2.1.25, RO 3.9/ SRO 4.2)
[)J 01......., , I/UA-f5 IflJiOlI 2\KA1/'f\ES-201 Examination Security Agreement Form ES-201-3 1.Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s)of date of my signature.
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-
        /\'
        -


I agree that I will not knowingly divulge any information about these examinations to any persons who have not'beeA au horized by the NRC chief examiner.I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).
          ,/../ .... ;,: f.


Furthermore, I am aware of the physical security measures and requirements (as documented in the facility licensee's procedures)
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)
and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
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).


2.Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s)of'f.'J.,p'l4JlJFrom the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or pro?ide performance feedback to those applicants who were administered these licensing examinations, except as specifically noted below and authorized by the NRC.JOB TITLE/RESPONSIBILITY(11"20 ES-201, Page 27 of 28
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)
:J-&r3 ES-201, Rev.9 Examination Security Agreement Form ES-201-3 1.Pre-Examination I acknowledge that I have acquired specialized knowledge about the NRC licensing examinations scheduled for the week(s)of as of the date of my signature.
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).


I agree that I will not knowingly divulge any information about these examinations to any persons who have not been authorized by the NRC chief examiner.I understand that I am not to instruct, evaluate, or provide performance feedback to those applicants scheduled to be administered these licensing examinations from this date until completion of examination administration, except as specifically noted below and authorized by the NRC (e.g., acting as a simulator booth operator or communicator is acceptable if the individual does not select the training content or provide direct or indirect feedback).
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


Furthermore, I am aware of the physical security measures and (as documented in the facility licensee's procedures)
          ), )
and understand that violation of the conditions of this agreement may result in cancellation of the examinations and/or an enforcement action against me or the facility licensee.I will immediately report to facility management or the NRC chief examiner any indications or suggestions that examination security may have been compromised.
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).


2.Post-Examination To the best of my knowledge, I did not divulge to any unauthorized persons any information concerning the NRC licensing examinations administered during the week(s)ofI{W',1f>&#xa5; From the date that I entered into this security agreement until the completion of examination administration, I did not instruct, evaluate, or performance feedback tothose applicants who were administered these licensing examinations, except as specifically noted below and authorized by..;the NRC.DATE NOTE (2)DATE SIGNATURE (1)--//--"
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)
JJ_fL!,.D (/tP:5fV).----
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)
cS::J!D IN it.cf!o!>-et,IU'tr I J.Vf,'p---------.7./l.Oc, (v TITLE/RESPONSIBILITY'OJu'--,.j"IJ&#xa5;X'
(CFR: 41.5/43.5/45.3/45.5)
no:,-\"I'''''h S<Jfv.Wire...'PRINTED NAMEJOB
11 Respond to failure of non-controlling 1 Stage pressure transmitter (1-AP-3); after transfer to  A,M,S,P 4 (SEC)
---1....., c:;.:::::r::(--J..t (;t'-I J--"--c:Jc::;:-..c::::::;.C/J......,;:::;0-<oc::;:-..-c:Jf,.....,*C/J.t---1......, l;:::;o....., G0r--f!::=l:='-!'::JI 1 4..........:;.c::::::;.i c::::::;.co...201-3 ES-201.Page 27 of 2B E::c:am!aaRon Security Agreement1.
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).


,.,....-J....-JS(."-'-r--"...---"-':"- I t".--u...........i'C
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)
.........d?Q;JU r c: ";...._.,\{.9'r&:.:I""Y'i"=:Z'"'i}
@ 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 .
(""ll[:.JJ.-
  * 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)
j-J To Ole ilest ormy)did not divulge to any unauthorized psrscn1S:aJ'iY inforrnaficmlie NRC ioensinQ eX3JnjnaliOlEadu:iriislEred
(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)
" du:mg the-,veek(SJ offe/Vt-II4e J e,ptJ From the date rna.tJ entaretllnto thIs security agresment urmr iDe
(R)CA      11 11 1 (S)imulator
..of admfnislralion,*an notevaloote, or pl'tmde: pedormance feedback Ie 1bose applicants MiDadminlstered lbese licensing except as spec::mcillr noted belOW'and autfmriz-oo by the NRC.ESr201 1.
          /'
          ,I
          ,J


I at:knowledae thal[have acqnire:rJ speciaflZed knDWJBdQeaboul
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)
!he.NRC HO"'..oslng exanfirla"tians S'Chedu.led fortbe we:elt{s)of date of my si,g nature..I-agree-that 1 yAJl nat knOl'JingTy dfttwge-any inforr.natian abC1ll these-emm1natiollS ill any persons..mo have not bee[lized by the NRC t:hief exarnfrter-f lImieisland fum 1 3m nat to Ql provide_fee-doock to those appica nts scheduledbe administered" these-fiDm this date until CD.n"1Pletion of exam1natio:n except aB s.peci&sect;l:airy Ti01ed below anti autnorizsd.by 1he l\!RC (e..g..acmg as a simt.d.a1o.r booth operator or communica1n.ris aC03'p1able if ihedi.:Jes not serect tbe Ilairiing content Dr provide dEed: or indirect I am zwar:e of Ihe physical ser.mity measures and requirements (as rlocumented in tile tacmty ucensee's prccetMes)
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).
and ende15tand that'Violati'an of1be oonditions ofti'lrs agreemern may resUiin canceOa"fumeX2m&#xa5;nalioos amtIor an enforcement act&m ag:ins1 me.or ibe faclt1tv r&#xa3;censee..
r vdI imm:eam1.ety report to faclfIy mEI'la'gEment or ti1e NRC ch1ef examiner-any ind.k:aficms or suggeslJons that e:xam1aafion nzayhal?e been_d..2.Pnst-Exall'liMlixt
.(J)FJEs 13.-__----..-L-_14---------------_..;.....-
-_._15..-----NOTES: CD 61JL'lS,A&sect;K'N:>k'J.fd 1 r 0-+ af\t l'7'5-==:r:t::I.IJ J:::: 0':>':r a..s..J:Q.:::->:::::::>-&#xa3;:II:::: LJ,..j--:I-<:lC<:;.>--"'::c: C,...:}LL-J t--c:z::;: 'LIJ....b-::;t t..L.I:'-I;;=:11:0:::z:::::r D-<C cr::::>--.::::J1'":'J:;:t ex;:::..........<:::::l-InS)c......n--;lI:--.J........0oC'J0.-.:::::::;:..LJ ,Si<--J'I ES*301 Administrative Topics Outline Form ES*301*1 Facility: North Anna Power Station Examination Level: Combined (See Below)Date of Examination:
_--.;;;.6;..;;;;/2;;...;;;.0...;;.,0...;;;.,8
__Operating Test Number:_----=-1_Administrative Topic (see Note)Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code*M,R N,R N,R N,R M,R Describe activity to be performed (KA)Determine the Quadrant Power Tilt Ratio by hand calculation (1-PT-23)and determinemaximumallowable power level based on the calculation.(ALL)(G2.1.7, RO 4.4/SRO 4.7)Determine minimum RHR flow based on time after shutdown 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)Evaluate and apply Tech Specs and procedure requirements based on UNSAT condition from QTRL Y PORV Block valve surveillance (1-PT-44.7).


(1)(ALL)(G2.2.40, RO 3.4/SRO 4.7)Select appropriate RWP and calculate Stay Time (ALL)(G2.3.7, RO 3.5/SRO 3.6)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 required.*Type Codes&Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank3 for ROs;00 for SROs&RO retakes)(N)ew or (M)odified from bank1)(P)revious 2 exams1;randomly selected)(1)-For SRO Candidates there is one additional element that is not included in the RO JPM.
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


ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: North Anna Exam Level: ROSRO-I D SRO-U 0 Control Room Systems@(8 for RO);(7 for SRO-I);(2 or 3 for SRO-U, including 1 ESF)Date of Examination:
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)
Operating Test No.: 1 System 1 JPM Title (KA)a.Emergency Borate for stuck rods following Reactor Trip (1-ES-O.1)(MOV-1350 will not open)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)b.Respond to misaligned control rod, during realignment rod will drop causing negative rate trip;(turbine fails to trip causing SI actuation, SI fails to automatically actuate but can be manually actuated).
(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).


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)c.Transfer an emergency bus from an emergency diesel generator to a reserve station service 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 1 45.5 to 45.8)d.Respond to Loss of RHR in Mode 4 (1-AP-11)005-A2.03, Ability to (a)predict the impacts of the following malfunctions or operations on the RHRS;and (b)based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
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)
RHR pump/motor Malfunction (2.9/3.1)(CFR: 41.5 1 43.5 1 45.3/45.5)e.Respond to failure of non-controlling 1 st Stage pressure transmitter (1-AP-3);after transfer to 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)f.Add Nitrogen to PRT 007-A 1.02, Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits)associated with operating the PRTS controls including:
@ 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)
Maintaining quench tank pressure (2.7/2.9)(CFR: 41.5/45.5)g.Respond to Recirc Spray Heat Exchanger radiation monitor alarm (1-AP-5)073-A4.01, Ability to manually operate and/or monitor in the control room: Effluent release (3.9/3.9)(CFR: 41.71 45.5 to 45.8)h.Respond to loss of 1 or more Circ Water Pumps (1-AP-13)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:
(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)
Loss of Circulating Water Pumps (2.5/2.7)(CFR: 41.5 I 43.5 I 45/3 I 45/13)In-Plant Systems@(3 for RO;3 for SRO-I;3 or 2 for SRO-U)i.Open the residual heat removal heat exchanger cooling water return valves using a jumperAP-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 miti.gate the consequences of those malfunctions or operations:
,- (R)CA iSiimulator 1 1 1 I!. 1 (,
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 1 43.5 1 45/3 1 45/13)j.Re-energize a 120-volt vital bus from its inverter (1-MOP-26.6, 0-AP-10)057-AA 1.01, 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 41.7 145.51 45.6)k.Trip the reactor locally by opening the Reactor Trip Breakers or the rod-drive motor generator 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 (4.1/4.0)(CFR 41.7 1 45.5/45.6)Type Code*A,M,S,E,L A,N,S,EN D,S A, M, P, L, S A,M,S,P D,S,P D,C,E N,S D,E,R D,E A,D,E Safety Function 2 6 4 (Pri)4 (SEC)5 7 8 8 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power
          \.
/Shutdown (N)ew or (M)odified from bank including 1(A)(P)revious 2 exams (similar topic)(R)CA (S)imulator Criteria for RO/SRO-I/SRO-U 4-6/4-6/2-31/1/1-/-/1 (control room system)1/1/1 2/2/13/3/2 (randomly selected)1/1/1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: North Anna Exam Level: RO D SRO-ISRO-U 0 Control Room Systems@(8 for RO);(7 for SRO-I);(2 or 3 for SRO-U, including 1 ESF)System/JPM Title (KA)Date of Examination:
Operating Test No.: Type Code*6/2008 Safety Function a.Emergency Borate for stuck rods following Reactor Trip (1-ES-0.1)(MOV-1350 will not open).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)b.Respond to misaligned control rod, during realignment rod will drop causing negative rate trip;(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)c.Transfer an emergency bus from an emergency diesel generator to a reserve station service transform er 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)d.Respond to Loss of RHR in Mode 4 (1-AP-11)005-A2.03, Ability to (a)predict the impacts of the following malfunctions or operations on the 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)e.Respond to failure of non-controlling 1 st Stage pressure transmitter (1-AP-3);after transfer to 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)f.Not used for SRO-I candidates g.Respond to Recirc Spray Heat Exchanger radiation monitor alarm (1-AP-5)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)h.Respond to loss of 1 or more Circ Water Pumps (1-AP-13)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 (3 for RO;3 for SRO-I;3 or 2 for SRO-U)i.Open the residual heat removal heat exchanger cooling water return valves using a jumperAP-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)j.Re-etlergize a 120-volt vital bus from its inverter (1-MOP-26.6, 0-AP-10)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)k.Trip the reactor locally by opening the Reactor Trip Breakers or the rod-drive motor generator breakers 029-EA 1.12, Ability to operate and monitor the following as they apply toaA TWS: M/G set power supply and reactor trip breakers (4.1/4.0)(CFR 41.7/45.5/45.6)A, M, S, E, L A,N,S,EN D,S A, M, P, L, S A,M,S,P N/A D,C,E N,S D,E,R D, E A,D,E 2 6 4 (Pri)4 (SEC)N/A 7 8 8 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power
/Shutdown (N)ew or (M)odified from bank including 1 (A)(P)revious 2 exams (similar topic)(R)CA (S)imulator Criteria for RO/SRO-I/SRO-U 4-6/4-6/2-3 t 1/t 1/t 1-/-/t 1 (control room system)1/1/t 1 2/2/t 1 3/3/2 (randomly selected)1/1/t 1 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: North Anna Exam Level: RO D SRO-ID SRO-UControl Room Systems@(8 for RO);(7 for SRO-l);(2 or 3 for SRO-U, including 1 ESF)Date of Examination:.....
__Operating Test No.: 1 System 1 J PM Title (KA)a.Not used for SRO-U candidates b.Respond to misaligned control rod, during realignment rod will drop causing negative rate trip;(turbine fails to trip causing Sl 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 1 45.5 to 45.8)c.Transfer an emergency bus from an emergency diesel generator to a reserve station service 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 1 45.5 to 45.8)d.Respond to Loss of RHR in Mode 4 (1-AP-11)005-A2.03, Ability to (a)predict the impacts of the following malfunctions or operations on the 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 1 43.5 1 45.3 1 45.5)Type Code*N/A A,N,S,EN D,S A, M, P, L, S Safety Function N/A 2 6 4 (Pri)e.Not used for SRO-U candidates N/A N/A f.Not used for SRO-U candidates N/A N/A g.Not used for SRO-U candidates N/A N/A h.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)i.Open the residual heat removal heat exchanger cooling water return valves using a jumperAP-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 1 43.5 1 45/3 1 45/13)j.Not used for SRO-U candidates k.Trip the reactor locally by opening the Reactor Trip Breakers or the rod-drive motor generator breakers 029-EA 1.12, Ability to operate and monitor the following as they apply toaA TWS: MIG set power supply and reactor trip breakers (4.1/4.0)(CFR 41.7 1 45.5 1 45.6)D,E,R N/A A,D,E 8 N/A@All RO and SRO-l 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 (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power
/Shutdown (N)ew or (M)odified from bank including 1 (A)(P)revious 2 exams (similar topic)(R)CA (S)imulator Criteria for RO/SRO-I/SRO-U 4-6/4-6/2-31/1/1-/-/1 (control room system)1/1/1 2/2/1 3/3/2 (randomly selected)1/1/1
&#xa3;8-301 The operating test conforms with the previously approved outline;changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safetyfunctiondistribution).
 
Operating Test Number: 1 The There is no day-to-day repetition between this and other operating tests to be administered during this examination.
 
1.General Criteria e.It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.d.Overlap with the written examination and between different parts of the operating test is within
...a.Each JPM includes the following, as applicable:
initial conditions initiating cues references and tools, inclUding associated procedures reasonable and validated time limits (average time allowed for completion)
and specific designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that include:-detailed expected actions with exact criteria and nomenclature-system response and other examiner cues-statements describing important observations to be made by the applicant-criteria for successful completion of the task-identification of critical steps and their associated performance standards-restrictions on the sequence of steps, if applicable b.Ensure that any changes from the previously approved systems and administrative walk-through outlines (Forms ES-301-1 and 2)have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations)
specified on those forms and Form ES-201-2.3.Simulator Criteria The associated simulator operating tests (scenario sets)have been reviewed in accordance with Form ES-301-4 and a copy is attached.Printed Name/Signature a.Author b.Facility Reviewer(*)
c.NRC Chief Examiner (#)d.NRC Supervisor Date NOTE:*The facility signature is not applicable for NRC-developed tests.#Independent NRC reviewer initial items in Column"c'" chief examiner concurrence ES-301, Page 24 of 27 (.-ES-30 1 Operating Test Quality Form ES-30 1-3 Facilit: North Anna Power Station Date of Examination:
: 6/2/08-6/6/08&6/16/08-6/20/08 Operating Test Number: 1 Initials 1.General Criteria a b*c#a.b.c.d.e.The operating test conforms with the previously approved outline;changes are consistent with sampling requirements (e.g., 10 CFR 55.45, operational importance, safety function distribution).
 
There is no day-to-day repetition between this and other operating tests to be administered during this examination.
 
The operating test shall not duplicate items from the applicants'
audit test(s).(see Section D.1.a.)Overlap with the written examination and between different parts of the operating test is within It appears that the operating test will differentiate between competent and less-than-competent applicants at the designated license level.2.Walk-Throu h Criteria 3.Simulator Criteria The associated simulator operating tests (scenario sets)have been reviewed in accordance with Form ES-301-4 and a copy is attached.Each JPM includes the following, as applicable:
initial conditions initiating cues/" references and tools, inclUding associated proceduresV'
reasonable and validated time limits (average time allowed for completion)
and specificv'
designation if deemed to be time-critical by the facility licensee operationally important specific performance criteria that include:-detailed expected actions with exact criteria and nomenclature-system response and other examiner cues-statements describing important observations to be made by the applicant-criteria forsuccessful completion of the task-identification of critical steps and their associated performance standards-restrictions on the sequence of steps, if applicable b.Ensure that any changes from the previously approved systems andadministrativewalk-through outlines (Forms ES-301-1 and 2)have not caused the test to deviate from any of the acceptance criteria (e.g., item distribution, bank use, repetition from the last 2 NRC examinations)
specified on those forms and Form ES-201-2.a.Printed Name/Signature a.Author b.Facility Reviewer(*)
c.NRC Chief Examiner (#)d.NRC Supervisor Date NOTE:*The facility signature is not applicable for NRC-developed tests.#Independent NRC reviewer initial items in Column"c";chief examiner concurrence required.*ES-301, Page 24 of 27 er Station Date of Exam:: 6/2/08-6/6/08 Scenario Numbers: 1/2/3/4/5 a eratin Test No.: 1 1/0/1/0/2 5/5/6/5/3 3/1/2/2/1 osition.QUALITATIVE ATTRIBUTES Total malfunctions (5-8)EOP contingencies actions (0-2)Abnormal events (2-4)
Scenario;See Section D.S.d)Sequencing and timing of events is reasonable, and allows the examination team to obtain
.. 2.The scenarios consist most!of related events.3.Each event description consists of the point in the scenario when it is to be initiated the malfunction(s)
that are entered to initiate the event the symptoms/cues that will be visible to the crew the expected operator actions (by shift position)the event termination oint if a licable 1.11.All individual operator competencies can be evaluated, as verified using Form ES-301-6 (submit the form along with the simulator scenarios).
 
4.No more than one non-mechanistic failure (e.g., pipe break)is incorporated into the scenario wlthout,a,credibJe".
 
re.ce.din incident.such,.as
..a.selsruic,.event.
 
8.The simulator modelin is not altered.9.The scenarios have been validated.
 
Pursuant to 10 CFR 55.46(d), any open simulator performance deficiencies or deviations from the referenced plant have been evaluated to ensure that functional fidelit is maintained while runnin the lanned scenarios.
 
12.Each applicant will be significantly involved in the minimum number of transients and events s ecified on Form ES-301-5 submit the form with the simulator scenarios.
 
10.Every operator will be evaluated using at least one new or significantly modified scenario.All other scenarios have been altered in accordance with Section 0.5 of ES-301.7.If time compression techniques are used, the scenariosummaryclearly so indicates.
 
Operators have sufficient time to carry out expected activities without undue time constraints.
 
Cues are iven.ES-301, Page 25 of 27 ES-301 Transient and Event Checklist (Scenarios 1-4)Form ES-301-5 Facility: North Anna Date of Exam: 6/2/08-6/6/08 Operating Test No.: 1 A E Scenarios P V'M P E 1 2 3 4 T L N CREW POSITION CREW POSITION CREW POSITION CREW POSITION 0 I I T T N CSABSABSAB S A B I A A T R T 0RT 0RT 0 R T 0 M N Y 0 C P 0 C P 0 C P 0 C P L UTP M(*)ERIU RO RX 2 5 1 1 1 0 X SRO-I NOR 1,2 3, 4a.4a 1 111 D IIC 4,6,9;3,5,7''''2,4 1,3a'2,4,6 1,3,5, 2,4,?3,5, 4 4 2 SRO-U 1Q H, 17 7,868,9 6aD MAJ 8 8 v 6 6, 7 i Z T 7.2 2 1 TS ,.).................*.
ii....................
*...***.**ic/.!;;
022 ,:}....RO RX 2, 3 5 1 t11 0 D NOR 4a, 4a 111 SRO-I I/C 4,6,9 t.2,4, 2,4,6/2,'4,6442 X 10 7 8,9 6a SRO-U D MAJ 8'6*7 T 2 2 1/.'<.)i ii...........
);I'.).***.**;;TS>.\022..:.RO RX 2 3 5 1 1 1 0 D NOR 1 4a 4a111 SRO-I X I/C ,3,4,5.'1,2 1;2,3 2,3 442 SRO-U 6,7,9 ,,3a,4:4,6,8 4,5,6 D 10,11 7,8 9 6a,8 MAJ 8 6, 7 7221 TS 3a,5 1,4,52h3 0 2 2 RO RX 2, 3 5 1 110 D NOR 1 4a 4a11 1 SRO-I D IIC 3,4,5,1,2 2,3442 SRO-U 6,7,9 3a,4 3,4,6 4,5,6 X 10,11 7,8 8,9 6a,8 MAJ 8 6 7 7,221 TS 3a,5 1,4,5 4,5 2,3 0 2 2 NOTE: Numbers in bold are the IIC events that occur before the major event.Instructions:
1.Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type;TS are not applicable for RO applicants.
 
ROs must.serve in both the"at-the-controls (ATC)" and"balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (IIC)malfunctions and one major transient, in the ATC position.If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two IIC malfunctions requiredforthe ATC position.2.Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d)but must be significant per Section C.2.a of Appendix D.(*)Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.3.Whenever practical, both instrument and component malfunctions should be included;only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified for the applicant's license level in the right-hand columns.fl-pPL/C 1Wl.s WtLL b-s-r fYltfl.\ltuU.tt.4\-SF w fHa l TJ PEdLFt1flM
..
ES-301 Transient and Event Checklist (for Scenario 5)Form ES-301-5 I Facility: North Anna Date of Exam: 6/2/08-6/6/08 Operating Test No.: 1 I A E Scenarios P V P E 5 (Spare)T M L N CREW POSITION CREW POSITION CREW POSITION CREW POSITION 0 I I T T N CSA B S A B SABSA B A IAT R T 0 R T 0 R T 0RT 0 M N Y 0 C P 0 C P 0CP 0 C P L UTP M(*)E R I U RO RX 5a 1 1 0 X 1 1 1 SRO-I NOR 5a D IIC 2,4,5 3,544 2 SRO-U 7,8,9 7,9 D MAJ66 2 2 1 i l<******ii\:>\*****i....t t***************\****
....***>i.......1<......I....i 0 2 2 TS...................
....\*t....*.t........*...tti RO RX 5 1 1 0 D NOR 1 1 1 SRO-I IIC 2,4,544 2 X 7;8,9 SRO-U D MAJ 622 1 TS II Ie 022 RO RX 5a 1 1 0 D NOR 1 1 1 SRO-I X IIC 2,344 2 SRO-U 4,7,8 D 9 MAJ 6 2 2 1 TS 1,3,5 0 2 2 RO RX 5a11 0 D NOR 1 1 1 SRO-I D IIC 2,3 4 4 2 SRO-U 4,5,7 X 8,9 MAJ 6 2 2 1 TS 1,3,5 022 NOTE: Numbers in bold are the IIC events that occur before the major event.Instructions:
1.Check the applicant level and enter the operating test number andFormES-D-1 event numbers for each event type;TS are not applicable for RO applicants.
 
ROs must serve in both the"at-the-controls (ATC)" and"balance-of-plant (BOP)" positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C)malfunctions and one major transient, in the ATC position.If an Instant SRO additionally serves in the BOP position, one IIC malfunction can be credited toward the two IIC malfunctions required for the ATC position.2.Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d)but must be significant per Section C.2.a of Appendix D.(*)Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.3.Whenever practical, both instrument and component malfunctions should be included;only those that require verifiable actions that provide insight to the applicant's competence count toward the minimum requirements specified fortheapplicant's license level in the right-hand columns.
 
ES-301 Competencies Checklist Form ES-301-6 Facility: North Anna Date of Examination:
6/2/08-6/6/08 Operating Test No.: 1 APPLICANTS RO/BOP X RO X RO D RO D SRO-I D SRO-I X SRO-I X SRO-I D SRO-U D SRO-U D SRO-U D SRO-U X Competencies SCENARIO SCENARIO SCENARIO SCENARIO123412341 2341 2 3 4 3,3a 1,2,3, 1,2 1,2 3a 2,3 2,4 2,4, 3,3a 1,21,21,2 3,3a 1,2 1,2 1,2 InterpreUDiagnose 4,5,6 3a,4 3,4 3,4 4,6 4,5 6,7 6,6a 4,5 3 3,4 3,4 4,5 3,3a 3,4 3,4 Events 7,8,9 5,6,8 5,6 5,6 7,868 7 6,7 3a5,65,6 6,7 4,5 5,6 5,6 and Conditions 10,11 7,8 7,8 9,10 8,9 4,5 7,8 7,8 8,9 6,8 7,8 7,8 9 11 6,8 111,21,21,21,2 2,4, 2,3, 2,4 1,2 2,3 1,2 1,2 1,2 2,31,21,2 1,2,3 Comply With and 3,4 3,4 3,4, 3,4, 6,7 4,5 4a,5 4,4a 4,5 3,4 3,4, 3,4, 4,5 3,4 3,4, 4,4a,5 Use Procedures (1)5,65,6 4a 5,6 8,9 6 6,8 6,6a 6,7 5,6 4a 4a,5 6,7 5,6 4a 6,6a,7 7,8 8 5,6 6a,7 11 7 8,9 8 5,6 6,6a 8,9 8 5,6 9,11 9 8 11 7,8 7 11 7,8 1,2,3, 1,2 1,2 1,22,42,32,42,4 Operate Control 4,5,6, 3,3a 3,4 3,4, 6,7 4,64a,54a,5 Boards (2)7,8,9 4,6,8 4a 4a,5 8,9 6,8 6,6a 11 5,6 6,6a 7 7,9 7,8 1,2 1,21,21,2 3a 2,3 2,4 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1,2 Communicate3,3a3,3a 3,4 3,4 4,6 4,5 4a 4,4a 3,3a 3,3a3,43,4 3,3a 3,3a3,43,4 and Interact 4,5,6, 4,5,6 4a,5 4a,5 7,8 6 5,6 6,6a 4,5 4,5 4a,5 5,6 4,5 4,5,6 4a,5 5,6 7,8,9 8 6,7 6,6a 9,10 7,8 7 6,7 6,8 6,7 6a,7 6,7 8 6,7 6a,7 10,11 9 7,8 8,9 8 8,9 8 10 10 11 111,21,2 1,2 1,2 1,2 1,2 1,2 1,2 Demonstrate 3,4 3,3a 3,4 3,4 3,4 3,3a 3,4 3,4 Supervisory Ability (3)5,6 4,5 4a,5 5,6 5,6 4,5,6 4a,5 5,67,86,8 6,7 6a,7 7,8 8 6,7 6a,7 9,11 8 9,11 8 3a,5 1,4 4,5 2,3 3a,5 1,4 4,5 2,3 Comply With and 5 5 Use Tech.Specs.(3)Numbers in Bold are events that occur before the major malfunction Notes: (1)Includes Technical Specification compliance for an RD.(2)Optional for an SRO-U.(3)Only applicable to SROs.Instructions:
Check the applicants'
license type and enter one or more event numbers that will allow the examiners to evaluate every applicable competency for every applicant.
 
ES-301 Facility: North Anna Competencies Checklist Date of Examination:
6/2/08-6/6/08 Form ES-301-6 Operating Test No.: 1 APPLICANTS Competencies InterpreUDiagnose E'vents and Conditions Comply With and Use Procedures (1)Operate Control Boards (2)RO/BOP X SRO-I D SRO-U D SCENARIO 5 1,2 3,4 5,5a, 6,7 8,9 2,3 4,5 5a,6 7 1,2 3,4 5,6 7,8 RO X SRO-I X SRO-U D SCENARIO 5 2,4 5,5a 6,7 8 2,4 5,5a 6,7 2,4 5,5a 6,7 8 RO D SRO-I X SRO-U D SCENARIO 5 1,2 3,4 5,5a 6,7 1,2 3,4 5,6 7 5 1,2 3,4 5,5a 6,7 1,2 3,4 5,6 7 RO D SRO-I D SRO-U X SCENARIO Communicate and Interact Demonstrate Supervisory Ability (3)Comply With and Use Tech.Specs.(3)1,2 3,4 5,5a 6,7 8,9 2,4, 5,5a 6,7 8 1,2 1,2 3,4 3,4 5,5a 5,5a 6,7 6,7 1,2 1,2 3,4 3,4 5,6 5,6 7 7 1,4 1,4 5 5 Numbers in Bold are events that occur before the major malfuncti*on Notes: (1)Includes Technical Specification compliance for an RO.(2)Optional for an SRO-U.(3)Only applicable to SROs.
 
ES-401 Written Examination Quality Checklist Form ES-401-6 Facility: North Anna Date of Exam: 6/24/08 Exam Level: ROSRO[8J Initial 1.2.3.4.Item Description Questions and answers are technically accurate and applicable to the facility.a.NRC KlAs are referenced for all questions.
 
b.Facility learning objectives are referenced as available.
 
SRO questions 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).5.Question duplication from the license screening/audit exam was controlled as indicated below (check the item that applies)and appears appropriate: 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), 6.Bank use meets limits (no more than 75 percent from the bank, at least 10 percent new, and the rest new or modified);
enter the actual RO/SRO-only question distribution(s)
at right.Bank I'a./0 Modified New 1*;1/;(5'/;<3 Question psychometric quality and format meet the guidelines in ES Appendix B.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 justified.
 
The exam contains the required number of one-point, multiple choice items;the total is correct and agrees with the value on the cover sheet.CIA'to/I Cf Memory 3S/b Between 50 and 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 KlAs support the higher cognitive levels;enter the actual RO/SRO question distribution(s)
at right.References/handouts provided do not give away answers or aid in the elimination of distractors.
 
7.9.8.10.11.a.Author b.Facility Reviewer (*)c.NRC Chief Examiner (#)d.NRC Regional Supervisor
/Signaturel'll.M('1..-
tC 1.i rAA_f'IJ N\t'f-l l
[;l1u-f\iO/1/;II,1t/1//h IIAt'A',JlI"w.IUIA.1/.I!:\
-,/Date (:,!4LoK dlJ-l/oy Note:*The facility reviewer's initials/signature are not applicable for NRC-developed examinations.
 
#Independent NRC reviewer initial items in Column"c";chief examiner concurrence required.
 
ES*401, Rev.9 Written Examination Review Worksheet Form ES*401*9 1.2.3.Psychometric Flaws 4.Job Content Flaws Q#Stem Icuesl T/F I JOb-I Minutia I#/I Back-Focus OISt.Link units ward I 7.Explanation 5.Other Kl QA=I SRO Only 6.U/E/S Instructions
[Refer to Section 0 of ES-401 and Appendix B for additional information regarding each of the following concepts.]
1.Enter the level of knowledge (LOK)of each question as either (F)undamental or (H)igher cognitive level.2.Enter the level of difficulty (LOO)of each question usinga1-5 (easy-difficult)
rating scale (questions in the2-4 range are acceptable).
 
3.Check the appropriate box if a psychometric flaw is identified:
*The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).
 
*The stem or distractors contain cues(i.e.,clues, specific determiners, phrasing, length, etc).*The answer choices are a collection of unrelated true/false statements.
 
*The distractors are not credible;single implausible distractors should be repaired, more than one is unacceptable.
 
*One or more distractors is (are)partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).4.Check the appropriate box if a job content error is identified:
*The question is not linked to the job requirements (i.e., the question has a valid KIA but, as written, is not operational in content).*The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).*The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).*The question requires reverse logic or application compared to the job requirements.
 
5.Check questions that are sampled for conformance with the approved KIA and those that are designated SRO-only (KIA and license level mismatches are unacceptable).
 
6.Based on the reviewer's judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E}ditorial enhancement, or (S)atisfactory?
7.At a minimum, explain any"U" ratings (e.g., how the Appendix B psychometric attributes are not being met).Page 1 of 37 ES*401, Rev.9 Written Examination Review Worksheet Form ES*401*9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 UIEIS H 001G2.4.31 New 2DD DDD D Doo D E 1."c" is not credible because why would you state that rod motion is"allowed" in bank select and then say that you can ONLY use turbine load to match Tave and Tref, i.e., rod motion in bank select is not allowed?2.Re-word the stem question to include"in accordance with the annunciator response procedure." Suggestion:
Re-work 1 st part of each choice to ask for the effect on the lift/stationary/gripper coils.The second part of each choice should present the applicant with a choice of using rod motion in"Bank Select" or adjusting turbine load.Suggested re-work: Which ONE of the following describes how this failure will affect the control rod drive system, including the required action in accordance with the annunciator procedure?
A.The lift coils and movable gripper coils will both be de-energized.
 
Move the control bank in"Bank Select" to maintain Tave.B.The lift coils will be de-energized and the movable gripper coils will be energized at reduced voltage.Use manual turbine control to maintain Tave.C.The lift coils and movable gripper coils will both be de-energized.
 
Move the control bank in"Bank Select" to maintain Tave.D.The lift coils will be de-energized and the movable gripper coils will be energized at reduced voltage.Use manual turbine control to maintain Tave.FINAL RESOLUTION 5/29/08: Instead of gripper coils, the first part of each choice deals with whether rod motion is inhibited or not.The second part of each choice deals with temperature adjustment using either/or turbine load/rods in bank select.Also re-worded stem question to require lAW procedure.
 
Question is SAT.2 H 2DDD D D DDDDD E 003A4.07 Bank 1.Since the stem question does not specify"in accordance with the annunciator procedure" then"B" can also be argued as correct.Re-word the stem question as follows: Which ONE of the following is a required action in accordance with the annunciator procedure?
'FINAL RESOLUTION 5/29/08: Question re-worked to test both annunciator procedure requirements and also breaker status of seal bypass isolation valve.Licensee did not want the phrase"in accordance with the annunciator procedure" because guidance for the operation of this valve originated from a vendor technical bulletin.Question is SAT.3F2 DDDDD DDDD D D S 004G2.2.3 New Page 2 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s 5.Other 6 U/EIS SRO Only Q=KIAwardLink 3.Psychometric Raw s Stem Partial Focus 2 LOD (1-5)1 LOK (F/H)Q#4 H 2DDDDDDDD D D E 005K1.06 Modified 1.Add a question mark after the stem question.2.Re-word the question stem as follows: Which ONE of the following is the minimum RHR flow requirement for these plant conditions, including the reason for this minimum flow requirement in accordance with 1-0P-14.1, Residual Heat Removal?3.Add the word"surveillance" after the word flow in both"A" and"C." Note: OP-14.1 also states RHR pump discharge check valve chatter (in addition to SI accum check valve chatter.)FINAL RESOLUTION 5/29/08: Comments incorporated.
 
Question is SAT 5 H 2DDDDDD DDDD 006K2.02 New Enhancement 1.Re-word the stem question as follows: and its"required" breaker position?FINAL RESOLUTION 5/29/08: Comments incorporated.
 
Question is SAT.6 F 2DDDDDDDD DD 007A4.10 Modified S u 1.There is no way for the applicant to determine which valve seat leakage (safety or PORV)is causing the abnormal PRT level, pressure,&temperature conditions provided in the stem.Instead, the question is testing the applicant's knowledge of the differences in available instrumentation for safeties vs PORVs and is not a direct hit on the KIA.Suggestion for more closely matching KIA: Present the applicant with temperature indications and acoustic monitor indications in the stem.This may require re-work of 2nd half of each answer choice.2.Question is similar to SRO Q#79;however, the SRO question deals with the unit at 100%power and has level and pressure stable.The PRT pressure in both questions is 14 psig though.FINAL RESOLUTION 5/29/08: Revised stem to include that acoustic monitor indications are normal.This eliminates the safeties.Also added knowledge of alarm procedure for second part of"A" and"C".Question is SAT Page 3 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raws Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E'S 7 Hooo D D oDD o u 007K3.01 New 1.The KIA is knowledge of the effect that a loss or malfunction of the PRT will have on the containment.
 
The question asks for how a level transmitter calibration error will affect the available volume in the PRT should a PORV lift occurs.2."B'" and"0" are not plausible because the time to rupture will be affected regardless of whether the applicant correctly or incorrectly determines the available volume.How can the rupture time not be affected?3."A" is not plausible because the stem indicated that the level reading is lower than actual;how can there be more volume available?
LOD=1 due to above com ments If need be, discuss changing KIA wi licensee.FINAL RESOLUTION 5/29/08: The question was revised to ask how containment sump level is affected and also the control room indications for containment radiation following a PRT rupture disc failure to burst.Question is SAT.8 H 2 o oDD DDDD*0 D D E 008AA2.24 New 1.Is steam dum p steam pressure mode controller normally set to 1005 psig?Will the applicants be expecting to see 1005 psig (vs 1010 psig)?Consider providing the as-designed steam pressures in the choices versus thereadability-values." Discuss wi licensee.2.Are the atmospheric dump valves set to start opening at 1 035 psig?(for"0")FINAL RESOLUTION 5/29/08: Comments incorporated.
 
Question is SAT.9 F 2 D D D DDD D DDD E 008K4.01 New 1.The last bullet in the stem (1 H EDG operates as designed)is a potential cue and is not necessary to answer the question.2.Add"auto" before the word starts in each of the choices.3."0" currently is the only choice with"remains deenergized." In the first part of"0" change the choice to read"CC Pump1B auto starts immediately when Bus1H is re-energized.
 
In"C" and"0", change the 2nd part to"CC Pump 1A does not re-start automatically." FINAL RESOLUTION 5/29/08: Did not incorporate the word"auto" but this is not crucial.The distractor
"0" was revised as described.
 
Question is SAT.Page 4 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 1 2 3.Psychometric Raw s 4.Job Content Raw s 5.Other 6 Q#LOK LOD (F/H)(1-5)Stem Partial Job-Back-Q=SRO U/ElS Focus Link ward KIA Only 10H2DD DDDDD DDD E 009G2.4.4 Modified 1."A" and"0" are not plausible."A" is not plausible because the RVLlS full range at 94%.(a lower RVLlS level indication will make it plausible).
 
"0" is not plausible because there are no indications that would lead the applicant to believe a faulted SG exists.FINAL RESOLUTION 5/29/08: Stem RVLlS changed to 740/0 and"0" was changed to 1-ES-1.1.Question is SAT.11 H 2 D DDDDDD D D D u 010K5.01 New 1.The second half of"B" and"0" are not plausible since they both state to ensure charging and letdown flows are equal.(how can you draw a bubble this way?)As an alternative, is it procedurally acceptable/possible to lower level by reducing charging?2.Capitalize the first letter of each word in the title of 1-0P-1.1 3.Delete the word"at" in the following stem question: "Assuming PZR heatup rate is at..." FINAL RESOLUTION 5/29/08: "B" and"0" revised to include which way the potentiometer is manipulated.
 
Question is SAT.12 F 2DDD D D D D D D E 011EK2.02 New 1."B" is not credible since is no way that the charging pump (HHSI pump)can take a suction from the containment sump.2.Re-word the stem question: "Given these current plant conditions, which ONE of the following identifies the required ECCS and Charging pump alignment after the initial swapover to Cold Leg Recirculation is performed in accordance with 1-ES-1.3?" FINAL RESOLUTION 5/29/08: Eliminated HHSI suction from sump and re-worked question to send the low head SI flow to charging pumps.Question is SAT.Page 5 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 13 H 2 D DDD D DDD D u 012K6.04 Modified Enhancement 1."A" and"B" are not credible because the second half of each choice are subsets of"C" and"D." Re-word the stem as follows: "Which ONE of the following identifies the RPS permissive affected by this transmitter failure, including the minimum number of RCPs required to trip the reactor?" 2.Consider other ways to describe the pressure transmitter failure (second bullet)other than"sticks." For example, the pressure transmitter fails such that it indicates x psig.FINAL RESOLUTION 5/29/08: Added the word"ONLY" to"A" and"B" to eliminate subset issue.The word"sticks" does not create confusion with respect to indication in control room vs'actual transmitter value.Question is SAT.14 H 2DDD DDDDD D D E 013A1.07 New Enhancement 1.Re-word the stem question to eliminate the BOP recommendation.
 
Instead, ask the following: "Which ONE of the following identifies the AFW flow requirements in accordance with E-O and the adverse containment criteria?" 2.Delete the words"Adverse Containment Criteria were cleared/are still in effect" from each of the choices.3.In"C" and"0", put the word"total" in front.FINAL RESOLUTION 5/29/08: Comments incorporated.
 
Question is SAT.15 F 2 D DDDDDD D D u 013K4.15 New Enhancem ent 1.The second part of"A" and"B" are not plausible because the stem doesn't include any information which might lead the applicant to assume a problem with Train A exists.2.Delete the word"assume" in the stem.3.Place plant conditions in stem into bullet form.4.Does the general warning condition trigger a different alarm than the train specific safeguards trouble alarm(s)?FINAL RESOLUTION 5/29/08: Re-worked question to include knowledge of the red general warning light, i.e., lit or extinguished.
 
Question is SAT.Page 6 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5, Other Q=SRO KIA Only 6 U/EIS 16 H 2 D D D D DDD D D E 015AK2.07 Bank Enhancement 1.The second part of each choice is not needed to make the answer choices unique.2.In order to make"B" and"0" more credible, change the sealleakoff flow and seal dP values to STABLE (vs slowly rising).3.Re-word the stem question as follows: "Which ONE of the following identifies the RCP seal problem, including the required actions in accordance with 1-AP-33.1, Reactor Coolant Pump Seal Failure?" FINAL RESOLUTION 5/29/08: Comments incorporated.
 
Question is SAT.17 H 2DD D D DDDDDD u 016K1.02 New 1."A","B", and"C" are not credible because of the median select feature.Instead of Tcold failing completely low, put in some failure that requires applicant to know whether or not median select feature kicks in.FINAL RESOLUTION 5/29/08: Re-worked question to trouble shooting format such that applicant is required to identify instrument failure that could occur wlo affecting PZR heaters.Question is SAT.18 H 3DDDDDDDDD E 017A4.02 Modified Enhancement 1.Re-word the stem as follows: "Which ONE of the following identifies the required s.tatus of the RCPs in accordance with...?.., including the reason?" 2.Change the word"should" in each choice to"are required to be stopped" or"are NOT required to be stopped." FINAL RESOLUTION 5/29/08: Comments incorporated.
 
Question is SAT.Page 7 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 19 H 3 o D oDD D D oDD E 022A2.06 New Enhancement 1.Re-word the stem question as follows: "Which ONE of thefollowingidentifies the containment temperature that requires entering the action statement for Tech Spec LCO 3.6.5, Containment Air Temperature, and also identifies the required actions to be taken for these plant conditions in accordance with 1-AP-35?" FINAL RESOLUTION 5/29/08: Comments incorporated.
 
Question is SAT.20 F 2oo o D D DDDDD E 022AK3.03 New Enhancement 1.Re-word thestemquestion as follows: "Which ONE of the following choices identifies 1)an excess letdown lineup restriction and 2)the reason why reactor power must be monitored when placing excess letdown in service in accordance with 1-0P-8.5, Operation of Excess Letdown?" 2.Delete the following words from the 2nd part of each choice: "reactor power should be monitored because.." FINAL RESOLUTION 5/29/08: Comments incorporated.
 
Question is SAT.Question LOK is Fundamental but licensee designates as higher.Regardless of licensee's designation, overall test is still within acceptable range for higher cog questions.
 
21 F 2DDDDDDDDDDD S 022K1.04 New This is Fundamental level because only testing knowledge of chilled water power supply.Licensee has designated as higher.Regardless of licensee's designation, overall test is still within acceptable range for higher cog questions.
 
Page 8 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychorretric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 22 H 2 D D DDD ooo o D u 025AA1.12 New 1.Iterating on 3 choices.Re-word the stem question and choices as follows: Which ONE of the following 1)identifies the status of the Heat Exchanger Bypass Valve (1-RH-FCV-1605)
and 2)predicts the trend on the core exit thermocouples?
a.1-RHR-FCV-1605 operating as designed Core Exit TCs increasing b.1-RHR-FCV-1605 operating as designed Core Exit TCs stable c.1-RHR-FCV-1605 failed Core Exit TCs lowering d.1-RHR-FCV-1605 failed Core Exit TCs increasing Ans: a 2.What is the status of RHR Pump1B?Do we need to state that RHR Pump"1A" is the only one in service?FINAL RESOLUTION 5/29/08: Suggestion incorporated.
 
Question is SAT.23 H 2 D oDDDD DDD u 026A4.01 New 1.Both"A" and"B" include"verify quench spray running" which is also included in choices"C" and"0".Change"C" and"0" to"QS is required.CDA is not required." 2.Re-word the stem question as follows: "Which ONE of the following identifies the current status of the Quench Spray Pumps and the required actions to be taken in accordance with 1-E-0?" 3.Question#25 (026 K2.01)identifies that a CDA occurred with containment pressure at 29 psia.This may compromise the integrity of this question (#23).Discuss wIthelicensee 4.Discussplausibility of"B" with licensee pertaining to stopping CC pumps.FINAL RESOLUTION 5/29/08: Question#25 revised to eliminate overlap wI this question.Re-worked choices to eliminate the subset issues.Stem question was not re-worded; however, this is not crucial.Question is SAT.Question LOK is Higher but licensee has marked as Fundamental.
 
Regardless of licensee's designation, overall test is still within acceptable range for higher cog questions.
 
Page 9 of 37 ES-401, Rev.9 WrittenExaminationReview Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s'Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 24 H 2DD D D D DDDDD D S 026AA2.01 Bank This is higher level due to analysis of predicting the makeup source.25H2 DDD DDDDDDD D S 026K2.01 New Potehtial overlap with Q#23.FINAL RESOLUTION 5/29/08: Stem revised to eliminate containment pressure overlap issue.Question is SAT.26 F 2 D D D D D DDDD D D S 027AG2.2.42 Modified When a question is designated as Modified, then the originalquestionshould normally be provided.If the statistics do not show that this is a limitingitem,then there is really no need to have the original question.27 F 2 D DDDDD DDD D u 028K3.01 New 1.Answer choices are using the words"should".We can only test the applicants on what they are"required" to do.Have licensee check procedures and if possible, change the wording of all answer choices to state what the operators are"required" to do.2.KIA Match: Have the licensee explain how knowledge of a loss of a HRPS is being tested.It appears to me that all the H2 recom biners are available and ready for use.3.Discuss whether the applicant has enough information in the stem to deduce that H2 concentration is>0.5%.It may be necessary to place this in the stem because operators should not be placing H2 recombiners in service when H2 concentration is<0.5%>, even though it is less than 40/0.FINAL RESOLUTION 5/30/08:[Hydrogen]
designated as 3&deg;!cJ in stem;loss of H2 combiner incorporated in stem;and"required" vs"should" incorporated.
 
Question is SAT.Page 10 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 28 F 2 D D DDDDDDDD E 029EK1.05 Bank Is timeline clear?This may make a difference in how the applicant answers the question.Clarify that question is asking within 30 seconds of the ATWS.FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.29 F 2 D DDD DDDDD E 029K4.03 New 1.If ALL automatic actuations have taken place, then how can 1-HV-F-4A and 4B auto start?(The only way is if ALL auto actions had not actuallyoccurred,which would contradict the stem.)[Similar comment for"A" and"B".If ALL auto actuactions have taken place, then why would the fans trip?-auto actuations could easily be construed as auto actions.]2.The second part of each answer choice is not needed to make each answer choice unique.Delete the second part of each answer choice and add to"A" that the fans do not auto start after tripping.3.Re-word the stem question: "Which ONE of the following predicts how these containment conditions will affect the containment purge systems?" FINAL RESOLUTION 5/30/08: Stem question resolved to include the final status (i.e., after all auto actions have transpired).
 
Question is SAT.30 H 2 D D DDDDDDD u 032AK3.01 Bank 1.Subset issues exist with"C" and"0".The second piece of"C" and"0" are not mutually exclusive.
 
If 48 hours is allowed to restore the channel to operable, then IR and PR Nis would still be present to provide necessary protection.
 
2.Is the second part of"A" RO knowledge?
3.How is"0" plausible when it is common knowledge that we will not test them closed book on a 48 hour action statement?
4.Add"in accordance with" to the stem question.FINAL RESOLUTION 5/30/08: Revised distractors for"C" and"D." RO knowledge of overlap requirements can be used to arrive at correct answer"A".Question is SAT.Page 11 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/6'S 31 H 2 DDDD DDDDDD u 033K4.05 Bank 1.Stem uses the word"preferred";
applicant can potentially argue"0" as being correct.Provide reference material that'clearly states order of preference.
 
Discuss wi licensee 2.Why is leakage being tesJed in the second part of"A" and"B" and evaporation being tested in the second part of"C" and"D"?It would be better to test the same parameters in the second half of A&B as in C&D.Recommend using evaporation in A and B also.FINAL RESOLUTION 5/30108: Revised question to include a calibration error for PG water to blender flow transmitter.
 
Comments incorporated.
 
Question is SAT.32 H 2 DDDDD D D D o o D E 036AA1.01 New Answer is worded as what the operator"should" do-we need to test on what the operator is"required" to do.I looked at overlap with Q 29(029K4.03)
and I think that it is OK.Include instrument
#s in the stem and choices.Re-word stem question to encompass manual actions listed in"B" and"0" FINAL RESOLUTION 5/30108: Did not include instrument number (unnecessary).
 
Comments incorporated.
 
Question is SAT.33 F 2 DDDDD D DDDDD S 039G2.1.32 New 34 H 2DDDD o D D D D D E 041K6.03 New 1.Distractor"C": Does your steam dump system ever have 2 banks modulating?
Or does only one bank modulate after the previous bank gets full open?If two banks never modulate, then this distractor would not be plausible.
 
2.Distractor
"0": On some load reject events, not a turbine trip, do all four steam dumps ever open?Is this possible?3.Does"tripped open" mean"fully open" to all your applicants and operators?
Your lesson plan uses the terminology of"full open".FINAL RESOLUTION 5/30108: Distractors re-worked.
 
Licensee provided verbal reason why two banks modulating was plausible.
 
Question is SAT.Page 12 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/6'S 35H2 DDDDDDD D D E 054AK3.01 New 1.Oistractor
"0": Have licensee expound on the justification of plausibility for this distractor.
 
2.Operationally, what is the maximum power licensee will realistically allow when operating with only 1 feedpump?31.1 doesn't state prerequisite/initial conditions for removing feedpump)FINAL RESOLUTION 5/30/08: Added"motor" windings to"0" (vs pump windings).
 
Licensee said 750/0 power can be supported with one feedpump out of service.Question is SAT.36 F 2DDDDD D D D D D D S 055A3.03 New 37H2 DDDDDDDDDD 0 S 055EA1.06 New 38H2 D DDD D D D D D D 0 S 056AA2.72 New See overlap comment on Q44 (061 K2.01).FINAL RESOLUTION 5/30/08: Re-worked question to ask about pump motor availability vs valve power supplies.Question is SAT.39H2DDDD DDDDD D E 057AG2.4.45 New 1.Is the E-Plan info being tested considered to be RO knowledge at NA?If NA staff does not take issue with this knowledge being required of an RO, then the question may be OK.Can NA provide any learning objectives or job function information that would support asking this question to an RO?2.Interesting method for meeting the KIA because the lack of alarms=ability to prioritize and interpret the significance of each annunciator or alarm.(loss of annunciator alarm does come in though).FINAL RESOLUTION 5/30/08: Licensee explained that RO's perform E-plan notifications at North Anna.Question is SAT.Page 13 of 37 ES-401, Rev.9 Written Examination Revie'w Worksheet Form ES-401-9 4.Job Content Raw s 5.Other 6 U/6'S SRO Only Q=KIAwardLink 3.Psychometric Raw s Stem Partial Focus 2 LaD (1-5)1 LOK (F/H)Q#40 H 2DDDDDDDDD D E 058AK1.01 Modified Add"in accordance with..." to the stem question.FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.41 H 2DDDDDDDD DDD S 059K1.02 Modified 42 F 2DDDDDDDDDDD E 060AA2.05 New 1.Typo in question: "of of'2.Use the title of the actual alarm in all answer choices.Which Monitor causes the Process Vent Stack A&B HI HI?3.Should each choice be Hi Hi (vs only Hi)?FINAL RESOLUTION 5/30/08: Licensee verified that Hi setpoint causes actuations.
 
Comments incorporated.
 
Question is SAT.43 F 2DD DDDDDDDD o E 061AG2.4.3 New 1.Is the green light labeled on the monitor?If so, discuss adding the label to the answer choices.2.Specify name of annunciator in answer choices.3.Is this really a"post accident" monitor?FINAL RESOLUTION 5/30/08: Re-worked to include actual name of lights on rad monitor drawers (i.e., SAFE/RESET).
 
Question is SAT.44 F 2DDDD D D DDDD u 061 K2.01 New Question overlaps with Q38 (056AA2.72).
 
Information can be used by one to help answer the other.This question is only unsat because of the overlap issues.FINAL RESOLUTION 5/30/08: Overlap issues corrected in other question 38.This question remains.Question is SAT.Page 14 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 45 F 2DDD D D DDD D D E 062G2.1.27 Bank 1.Is there any way for"C" to be successfully argued as correct?Discuss with the licensee.2.Is SOLA an acronym?In the distractor analysis it is in all CAPS.Typos are usually a clue that it is not the correct answer.FINAL RESOLUTION 5/30/08: Distractors re-worked to ensure that applicants could not confuse the generic term"disconnect switch." Also included knowledge requirement to ascertain fire location.Question is SAT.46 F 2DDDD D D D-DDD D S 062K3.03 New No overlap concernwithQ40.47H2DD D D D D DDDDD E 063K4.01 Bank Add the word"auto" before transfer FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.48 H 2 D D DD D D D D D D E 064K3.02 New Distractor"A": Aux Oil Pump does not appear to be a plausible distractor.
 
This distractor may need to be replaced.Discuss with licensee.FINAL RESOLUTION 5/30/08: Revised distractor to include DC fuel oil pump.Question is SAT.49 F 2DD D DDDDDDD E 065AK3.03 Bank 1.Distractor"B": SG shrink to the point of a Rx Trip signal does not appear plausible.
 
On a turbine trip or large load reject, steam flow is much less than feed flow.Even though shrink will occur, the SGs still have a large feed supply.2.Re-word the stem question: "Which ONE of the following identifies the reason for manually closing the main steam trip valves?" FINAL RESOLUTION 5/30/08: Stem question re-worded.
 
Licensee explained plausibility of shrink.Question is SAT.Page 15 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/ElS 50 H 2DD D D D DDDD E 071A2.02 New 1.Question statement should state: "Which ONE of the following describes the preferred method for controlling the WGDT release flow rate in accordance with 0-OP-23.2, procedure title?" 2.Why is manual control plausible?
Do other types of releases typically occur with manual control?FINAL RESOLUTION 5/30108: Procedure states"preferred." Question stem re-worded to include in accordance with procedure.
 
Licensee explained why Manual control was plausible.
 
Question is SAT.51 F 2 D D D D DDD D DDD S 073A1.01 Bank 52 F D D D D DDDD D u 073K5.02 Modified 1.Tough KIA to match.Question does not match KIA because it does not test how a process rad monitor is affected by radiation intensity as the distance to the source changes.Are there any rad monitors that can be affected by radioactive trash in transit?Have there been past situations where someone has carried a bag of trash past a process rad monitor that caused an inadvertent actuation?
2.Are they testing a PRM?Maybe if you consider portable dose rate detector?3.Distractors"A" and"0": There is no reasonable misconception that could lead to these two answers.Discuss with licensee.(as a result LOD=1)FINAL RESOLUTION ON 6/9/08: Licensee re-worked question to test inverse square rule for radiation intensity and also to test reflash capability on a multi-input annunciator associated with radiation detectors.
 
Question is SAT.Page 16 of 37 ES-401, Rev.9'Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/6'S 53 H 2DD DDDDD D D u 076A1.02 New 1.Can the last part of"0" be deleted?Is it needed to make the answer choice unique?2.Is it possible that the crew could address H2 Temp Alarm first, thereby making"A" correct?3.Are Bearing Cooling Tower fans normally running?AP-19 step 4 states that if they are already running, then the RNO would not be performed.
 
Could this lead to making"A" arguably a correct answer choice?4.Question tests the INITIAL actions, but the question is not worded to test the initial actions in accordance with a specific procedure.
 
This leads to many questions about alternate correct answers.Does the question need to be tightened?
Can it be tightened in approximately its current form without damaging plausibility?
Discuss with licensee.5.Why are the distractors plausible?
Starting fans is such a simple first action.I am asking myself why I would not always try this first.Discuss with licensee.FINAL RESOLUTION 5/30/08: Last part of"0" was deleted.Stem question re-worded in accordance with procedure to address comments.Stem modified to include initial conditions with 3 fans running in slow speed.Discussions wi licensee determined that all distractor actions are prescribed by AP procedure.
 
Question is SAT.54 F D DDDDDDDD D u 076AK2.01 New 1.Distractor Plausibility:
The only answer choice that is credible is the correct answer.This is the only monitor associated directly with the primary coolant.(as a result LOD=1)2.Suggestion:
Is there any way to place a standard amount of SG tube leakge into the stem (an amount that the plant would commonly run with)and test some other monitors like condenser offgas, N-16s now in the presence of some tube leakage, and another monitor?Maybe the plant conditions in the stem would need to be adjusted to also ensure only one correct answer.FINAL RESOLUTION ON 6/9/08: Question re-worked to exclude the containment radiation monitor.Question now tests knowledge of condenser air ejector rad monitor and N16 rad monitors following a tube leak with abnormal RCS activity.Question is SAT.,55F2DD D o DDDDDD E 077AA1.01 New 1.Discuss the possibility of placing::".,...in accordance with AP-8" at the end of the question statement to tie the answer directly to the procedure.
 
2.When would the plant ever operate with voltage regulators in MANUAL(exceptfor maintenance)?
The two answer choices (B&D)with MANUAL may not be plausible.
 
Discuss with licensee.FINAL RESOLUTION 5/30108: Comments incorporated.
 
Manual is plausible.
 
Question is SAT.Page 17 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 56 F 2DDDDD DDDDD D S 078A4.01 Bank 57 F 2 DDD D DDDDDD E 078K4.03 New 1.It appears that each of the two alarms in the answer choices are to be evaluated independently of the other alarm.In other words, the first alarm in answer choice"A", is unrelated to the second alarm;however, they both cause a compressor trip.If this is the case, then it may be beneficial to clarify this in the question.2.Re-word the stem question to ask for which alarms are"indicative" of a compressor trip (vs cause a compressor trip)FINAL RESOLUTION 5/30/08: Question stem re-worked to include fill-in-the-blank to allieviate confusion.
 
Question is SAT.58 H 2 D D DDDDD D D E 079K1.01 Modified 1.Discuss the possibility of placing::"....in accordance with AP-28" at the end of the question statement to tie the answer directly to the procedure.
 
2.When the answer choices state all"Instrument Air" compressors, does this mean all"Instrument and Containment Instrument" air compressors?
If so, should this be clarified?
3.Would it be possible to raise 88 psig to 92 psig in the stem?Would this damage the question in any way?This may help to raise the credibility of the actions that occur at 94 psig.FINAL RESOLUTION 5/30/08:'Yes, discussed with licensee;no clarification needed.Comments incorporated.
 
Question is SAT.59 F 2 DDDDDD DDD D E 103A3.01 New 1.TV-100A does not appear to be credible because it is a manual valve.It is also non-safety related, which is another large clue that this would not be chosen over the other answer choices.This distractor will likely need replacement.
 
Discuss with licensee.FINAL RESOLUTION 5/30/08: Distractor"C" revised.Question is SAT.Page 18 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/6'S 60H2 DooDDDD o E WE03EA1.2 New 1.Is it possible to change subcooling to 55F with no RCPs running and provide adverse containment parameters?
This may add more credibility to the first part of"A" and"B".2.The answer choices are worded such that the charging pump stopping is tied to"saturation", which may be correct;but the wording in the reference material refers specifically to not having to reinitiate SI flow due to a loss of subcooling margin (which mayor may not reach saturation).
 
Your idea is sound-I just want to ensure that the wording is such that it is unequivocally supported by the reference material.FINAL RESOLUTION 5/30/08: Stacked each choice to identify response and reason.Changed from 32 deg to 55 deg to add plausibility.
 
Also re-worded choices to describe loss of subcooling vs.saturation.
 
Question is SAT.61 H 2 o*0 o oDDDDD u WE05EK3.4 New 1.Distractor"A": Establishing AFW flow to the"B" SG is not credible.This distractor will need to be modified because ALL includes the"B" SG.2.Distractor"C": same comment as distractor"A".3.What plant conditions require adverse numbers to be used?(20 psia&1 E5 R/hr)-These parameters are not provided in the stem, so there is not much plausibility in the bleed and feed option based on SG.level.If values can be placed in the stem that would be close to the limits for adverse numbers, then the bleed and feed option may have more credibility.
 
4.The stem states that all AFW flow has been lost.How can"A" and"B" be possible (Le., establish AFW flow)?Are all the stem conditions necessary if the question is testing the overall H.1 strategies?
FINAL RESOLUTION 5/30/08: Re-worked question to require knowledge of limiting thermal stresses or maintaining heat sink.Question is SAT.62 H 2DDD D o DDD D o D S WE09EA2.1 New Page 19 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 63 F 2DDDD o DDDDD E WE12EK2.1 Modified 1.Most cooldown rates are given on an"in any given hour" basis, vice a"per hour basis." Your procedure is clear on a"per hour" basis.Will there be any confusion on the applicant's part due to any terminology inconsistencies between the procedure and tech specs?2.It is usually better to tie the correct answer choice to a procedure:
1-ECA-2.1.
 
In this case, the question needs to specifically ask for the guidance in 1-ECA-2.1.
 
This is important to ensure a clear difference between"C and"0".3.To be very clear"0" should state ALL SGs are required to be maintained
<500/0.4.Also, for clarity and consistency,"C" should state"to state ALL SGs".FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Discussed wi licensee.Question is SAT.64 F 2 D D DDD D DDDD E WE15EK2.1 Bank 1.Re-word the stem question: "Which ONE of the following water systems is a potential source of'leakage to the containment and requires action to isolate in accordance with FR-Z.2?" 2.Does service water ever automatically isolate to containment?
If so, what causes?FINAL RESOLUTION 5/30/08: Plausibility issue resolved by revising all distractors.
 
Comments incorporated.
 
Question is SAT.65 F 2DD D*0 D o D o D u WE16EK3.1 Bank 1.At what pressure does containment spray actuate?If 13 psia is less than inside/outside recirc spray actuation, then the option of using inside or outside containment spray does not appear to be plausible.
 
Discuss with licensee."A" and"B" may need to be replaced/modified.(LOD=1 as a result)2.Applicant can potentially argue that there is more than one correct answer because it's never wrong to"evaluate" starting/placing/venting.
 
FINAL RESOLUTION 5/30/08: Changed 13 psia to 22 psia.Eliminated"evaluate" from each choice.Question is SAT.66 G2.1.20 Modified F 2DD DDD DDD DDD S Page 20 of 37 ES*401, Rev.9 Written Examination Review Worksheet Form ES*401*9 4.Job Content Raw s Q#1 LOK (F/H)2'LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/EJS 67 F 2 D.DDDDD D D D D D E G2.1.37 New 1.This question should be designated as (F)undamental.
 
The operator may be able to*nuke out why raising letdown temp, for instance, would add negative reactivity, but they are familiar enough with this, that they will likely answer the question using a memory level thought process.For instance, they likely know from memory that the procedure tells them to lower power for SDAFW Pump testing.FINAL RESOLUTION 5/30/08: Comment incorporated.
 
Question is SAT.68 G2.1.41 New H 2 DDDDDDD DDDu"A" and"C" are not plausible because control rods must be unlatched prior to internals being removed.Discuss with licensee.These distractors do not appear to discriminate at the appropriate level and may need to be modified.(LOD=1 as a result)Suggestion:
test whether control rod unlatching is considered a core alteration or a reactivity manipulation iaw 1-0P-4.1.FINAL RESOLUTION 5/30/08: Discussed w/licensee and the applicant must know definition of core alteration to ascertain control rod unlatching as"first" core alteration.
 
Question is SAT.69 G2.2.1 New H D D DDDDD D DDu 1.Distractor"C": Subcritical multiplication is occurring, but to speak of stabilizing power does not appear to be plausible.
 
Replace w/stabilize neutron count rate.2.Distractor"A": Not plausible because the stem tells the applicant that they are going to be above the ECP allowable boron concentration.
 
Waiting to allow the reactor to go critical above the ECC does not appear to be a credible misconception.
 
Discuss withlicensee.This distractor will likely need to be replaced/modified.
 
3.Distractor"B" is not plausible because if the stem conditions state that previous dilutions placed plant above ECC[8]w/o criticality, then why would they dilute even more?4.LOD=1 due to non-credible distractors.
 
5.This question should will likely be answered by most at the (F)undamental level.Theapplicant really only needs to have the procedure requirement committed to memory.6.The last bullet in the stem is confusing.
 
("Criticality is imminent above the ECC Upper[B].")Suggest clarifying the boron dilution was secured due to being above the[8]w/o criticality.
 
FINAL RESOLUTION 5/30/08: Re-worked question to eliminate timeline confusion and increase plausiblity of all distractors.
 
Question is SAT.Page 21 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychorretric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/EJS 70 F 2 D DDD D D D D 0DD E G2.2.39 Modified 1.Change the word"indications" (in the stem question)to"parameter values" 2.Not necessary to capitalize RCS UNIDENTIFIED LEAKAGE FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.71 F 2 DDD D DDD D00 U G2.2.7 New The Notes in the stem are"teaching", which is typically not allowed.With this information provided, the applicant can immediately discredit category 1/because"safety" is not affected due to"complexity"-startups are relatively simple evolutions.
 
Typically ICCE level of supervision is considered SRO knowledge.
 
Is this considered SRO knowledge at NA?Discuss with licensee.FINAL RESOLUTION 5/30/08: Re-worked question and changed all distractors.
 
Question is SAT.72 G2.3.15 Bank F 2DDDD D D D D D E 1.Question should be worded to tie the answer to the ARP: "...in accordance with AP-5.1." 2."A" is not plausible because the HP tech, as stated in the stem, has stated that rad levels are unchanged.
 
Discuss with licensee.Distractor may need to be modified/replaced.
 
FINAL RESOLUTION 5/30/08: Re-worked the distractors and changed stem question to include in accordance with procedure.
 
Applicant must have knowledge of Enable/Disable to answer correctly.
 
Question is SAT.73 G2.3.4 New F 2 DDDDDDDD D u 1.Extra period in fourth bullet in stem.2.Is this information SRO-only knowledge?
Is it appropriate to test ROs at your site on this knowledge?
Is there a learning objective or procedure requirement that supports this being RO knowledge at NA?3."B" and"0" do not appear to be plausible.
 
Are there dose limits that are in place for a group of people as a whole (outside of dose goals for a job)?Limits are typically applied on an individual basis.Discuss with licensee.(LOD=1 as a result)FINAL RESOLUTION 5/30/08: Question re-worked.
 
Question is SAT.Page 22 of 37 ES*401, Rev.9 Written Examination Review Worksheet Form ES*401*9 4.Job Content Raw s Q#1 LOK (F/H)2 Lao (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/EIS 74 F 2 D D DDDDDDD D u G2.4.32 New 1.Is the second to last bullet necessary information?
Is the stated alarm enoughforthe applicants to determine that the annunciators are not working?2."A" and C" are not plausible because when all alarms are lost, the plant must not be moved.FINAL RESOLUTION 5/30/08: Re-worked distractors to test requirement to station additional operator and logging requirements.
 
Question is SAT.75 G2.4.9 Bank H 2 D DDDD DDDD u 1.The stem does not provide the status of the"B" RHR pump-the applicant must make an assumption.
 
If"A" pump is airbound, does this airbound"B" also?2.Have licensee provide further justification why"A" is incorrect.
 
Add"immediately" start to"C" to make it totally incorrect, Le., prior to venting.4.What is the"appropriate attachment" in choice"D?" Can you include an attachment
#in choice"D?" (Attachment 8 or 10)5.This question may work, but issues need to be addressed to ensure that one and only one answer choice is correct and that an argument does not exist for no correct answer.We need to ensure that we provide enough information such that the applicant cannot claim that they were forced to make an assumption wrt the plant status.6.The KIA is not worded as it appears in NUREG-1122, Rev 2, Sup 1.The NUREG KIA states Knowledge of low power/shutdown implications in accident (e.g.;loss of coolant accident or loss of residual heat removal)mitigation strategies.
 
However, it appears that your question still meets the Rev 2, Sup 1 KIA.FINAL RESOLUTION 5/30/08: Licensee explained that"next actions" make"A" incorrect.
 
This was underlined in the stem question.Comments incorporated.
 
Question is SAT.Page 23 of 37 ES-401, Rev.9 WrittenExaminationReview Worksheet Form ES':401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 76H2DD D o D D D o u 005AA2.02 New 1.This is not SRO-only item because the second half of each choice is testing the action statement instead of testing the tech spec bases knowledge.(Note: RO must know tech spec knowledge of less than or equal to 1 hour action statements.
 
RO is also expected to know that rods must be within 12 steps of group step counter, i.e., information"above-the-line.
 
")2.Do not provide a reference to the applicant.
 
3.Delete the stem statement"The crew determines that recovery will be to restore the misaligned rod to its group." 4.Delete the portion of the question regarding rod speed during the re-alignment/recovery because it isn't being tested because of the initial speed already being available in each choice.5.Suggest re-word the question: Which ONE of the following identifies (1)the rod speed PRIOR to the blown fuse and (2)whether or not the H-8 control rod is operable?A.64 spm;H-8 is OPERABLE B.64 spm;H-8 is INOP C.72 spm;H-8 is OPERABLE D.72 spm;H-8 is INOP FINAL RESOLUTION 5/30/08: Re-worked to test inoperable versus operable instead of 1 hour requirements.
 
Comments incorporated.
 
Question is SAT.77 H 2DDDD-0 D D oDD E 005G2.2.40 New Enhancement 1.The second part of"A" and"B" are much too close (potentially the same).2.Do not provide a reference.
 
3.Stack answer choices to clean up appearance.
 
4.What is the status of"1 B" RHR Pump?FINAL RESOLUTION 5/30/08: Re-worded the second parts of"A" and"B" to differentiate.
 
Comments incorporated.
 
Question is SAT.Page 24 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-912 3.Psychometric Raw s 4.Job Content Raw s 5.Other 6 Q#LOK LaD (F/H)(1-5)Stem Partial Job-Back-Q=SRO U/E/S Focus Link ward KIA Only 78 H 3DDD D D D DDD E 006A2.03 New 1."B" choice is not plausible because the switchoverstatement (concerned with rocking up)is not plausible for the check valve leakage scenario.In other words, if there is check valve leakage, then accumulator contents would be diluted..therefore switch over time is not threatened.
 
Enhancement:
Re-word the stem and choices as such: "Given these levels and pressures, which ONE of the following predicts the reason for the alarms and identifies the tech spec bases for the accumulator level and/or pressure requirements?
a.Check valve leakage is occurring Ensures that subcriticality can be assured in a post-LOCA environment.
 
b.Check valve leakage is occuring Ensures that subcriticality can be assured following a main steam line break.c.Vent valve leakage is occurring Ensures that subcriticality can be assured in a post-LOCA environment.
 
d.Vent valve leakage is occurring Ensures that subcriticality can be assured following a main steam line break.Answer: a FINAL RESOLUTION 5/30/08: Re-worked choices to enhance distractor credibility.
 
Question is SAT.Page 25 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/EIS 79 H 2D*DDD Doo D u 007G2.2.44 New 1."C" and"0" are not plausible (writing a work request is always right..and won't mitigate problem).Choices"A" and"B" are always more reasonable to enSlJre PORVs are closed.(Why would you ever NOT ensure the PORVs are closed?)Also,"0" can be partially correct because it is never wrong to"refer" to a procedure.
 
2.Not SRO-only because choices also include responsive actions which an RO would be able to recognize; therefore, procedure selection is not required to answer the question.Basic event diagnosis is all that is needed to answer the question.Suggest the following:
Which ONE of the following describes the status of the pressurizer relief tank and also identifies the required actions in accordance with the alarm response procedure?
a.ONLY the pressure is high (Some other plausible procedure that is beyond RO knowledge)
(1-AP-16 is not plausible if PRT level is stable)b.ONLY the pressure is high 1-0P-5.7, Operation of the Pressurizer Relief Tank c.BOTH pressure and temperature are high (Some other plausible procedure that is beyond RO knowledge)
d.BOTH pressure and temperature are high 1-0P-5.7, Operation of the Pressurizer Relief Tank Answer:?FINAL RESOLUTION 5/30/08: KIA re-selected due to inability to write SRO level question.(064 G2.2.38).Question is SAT.80 H 2 D DDDDD D D D D u 008AG2.4.8 New 1."A" and"C" are not plausible because an operator would never leave the bus dead (until the EOP network is exited)with offsite power available.
 
.2."0" is not plausible (enter E2 faulted steam generator)
since the stem states that SG pressures are all 1000 psig.Suggestion:
Make one of the SGs faulted.The correct protocol is still to go to E-1.This will make"0" more plausible.
 
What AOPs can be performed concurrently with the EOPs?Are there any that can NOT be performed concurrently with the EOPs?FINAL RESOLUTION 5/30/08: Re-worked distractors to test SBO diesel use in accordance with procedure requirements.
 
Comments incorporated.
 
Question is SAT.Page 26 of 37 ES*401, Rev.9 Written Examination Review Worksheet Form ES*401*9 4.Job Content Raw s Q#1 LOK (F/H)2 3.Psychometric Raw s LOD (1-5)Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 81 H 2DDDD oDDDD u 012A2.04 New 1.Do not provide tech spec bases (only tech specs 3.3.1)2.If Tech Specs allow one train to be inoperable while on-line, then how credible is it that the online replacement of the power supply isn't permitted?
Discuss the credibility of"A" and"B" wi licensee.3.Delete the phrase in"A" and"B" which says"make notifications and preparations for plant shutdown".
 
This information is not needed to make the answer choices unique.4.Change time in"0" to 2 hours since this is a note in the required action"P" column (Le., note says that one train may be bypassed for up to 2 hours for surveillance testing, provided the other train is operable.)
 
Makes"0" more plausible.
 
FINAL RESOLUTION 5/30108: Comments incorporated.
 
Question is SAT.82 H 2 D D D D D D DDD E 017A2.02 New Enhancement 1.Delete the last bullet in the stem ("The crew is evaluating start of one RCP")Is this bullet necessary to show where they are in the procedure?
It diminishes the plausibility of"A" because why would they start ALL RCPs when they are evaluating starting ONE?Suggestion for re-wording question and choices: Given these plant conditions, which ONE of the following identifies the procedure action to mitigate this event?A.Remain in FR-C.1, start one RCP in an idle loop B.Immediately transition to SACRG-1 BEFORE opening pzr PORVs, Block Valves, and other RCS Vent Paths C.Remain in FR-C.1 , open pzr PORVs, Block Valves, and other RCS Vent Paths D.Open pzr PORVs, Block Valves, and other RCS Vent Paths and THEN transition to SACRG-1 Ans: c FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.Page 27 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/6'S 83H2 D D DDDDDD D u 025AA2.03 New 1.Is it necessary for the second bullet (in the stem)to include information that the crew entered 1-AP-11?If not, then consider re-wording as follows: "The crew isolates known RCS drain paths and maximizes charging flow." (Le., remove the number/title of the procedure)
2.Are"A" and"B" wrong enough?(Le., can they be argued as correct since it is conceivable that both AP s could be entered independently and concurrently?)
3.Re-word the stem question and the choices to"boil down" to the relevant knowledge.
 
Which ONE of the following identifies the required procedural guidance that will mitigate these plant conditions?
A.Perform 1-AP-11, Loss of RHR: Attachment 3, Determining Acceptable RHR Flow Reductions B.Perform 1-AP-11, Loss of RHR: Attachment 2, Minimum RCS Level for Indicated Flow C.Perform 1-AP-17, Shutdown LOCA: Attachment 7, Cold Leg Injection D.Perform 1-AP-17, Shutdown LOCA: Attachment 8, Hot Leg Injection Discuss wi licensee: 1.AOP entry conditions is RO knowledge 2.Applicant may be able to deduce that"C" is correct from simply knowing that the pzr surge line is on the hot leg.(RO knowledge)
3.This question deals somewhat with EOP mitigation strategy since it is a LOCA (albeit during shutdown conditions);
RO's are responsible for knowledge of EOP mitigation strategy.4.This question is borderline"okay" for SRO only because of the"C" and"0" knowledge req'd to choose Attachment 7 or 8 (procedure selection).
 
FINAL RESOLUTION 5/30108: Comments incorporated.
 
Question is SAT.Page 28 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/EIS 84H2 DDDD DDDD D u 026AG2.1.7 New Not SRO-only for the following two reasons: 1.RO is required to know tech spec equipment information"above-the-line." This question simply asks for whether an LCO is entered or not entered.This is RO knowledge.
 
2.AOP/EOP entry conditions is RO knowledge.
 
Is there some way to test the bases knowledge of what constitutes an operable CC subsystem into the question to make it SRO knowledge?
Suggestion:
Given these conditions, which ONE of the following identifies the required procedure and also identifies the design basis of the CC system in accordance with the tech spec bases?A.1-AP-15, Loss of Component Cooling Three CC subsystems are sufficient to accomplish a fast cooldown of one unit while maintaining normal loads on the other unit B.1-AP-15, Loss of Component Cooling Two CC subsystems are sufficient to accomplish a fast cooldown of one unit while maintaining normal loads on the other unit C.1-E-0, Reactor Trip or Safety Injection Three CC subsystems are sufficient to accomplish a fast cooldown of oneunitwhile maintaining normal loads on the other unit D.1-E-0, Reactor Trip or Safety Injection Two CC subsystems are sufficient to accomplish a fast cooldown of one unit while maintaining normal loads on the other unit FINAL RESOLUTION 5/30108: Comments incorporated.
 
Question is SAT.Page 29 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 3.Psychometric Raw s LOD (1-5)Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 UIElS 85 F 2 D D D D DDD DDD E 027G2.2.25 New Enhancement 1.In the third bullet and in choice"A">>use the word"solution" instead of"volume" 2.Re-word the stem question as follows: "Which ONE of the following describes how the current status of the Quench Sprayl Chemical Addition Tank affects the plant during a design basis LOCA in accordance with the tech spec bases?" 3.Delete the phrase"...and affects the ability to maintain Iodine at acceptable levels following a DBA LOCA." from the second half of"C" and"0" because this information is not necessary to make the answer choices unique.FINAL RESOLUTION 5/30108: Comments incorporated.
 
Question is SAT.86 H 3DDDDD DDDD E 034A2.03 New Enhancement 1.Provide only Tech Spec Figure 3.7.18-1, Burnup Credit Requirements.
 
Do not provide tech specs or tech spec bases.2.Re-word the stem question as follows: "Which ONE of the following identifies the minimum required actions in accordance with tech specs 3.7.18, Spent Fuel Pool Storage, including the bases for the action(s)?" Re-word the choices as follows: A.ONLY one fuel assembly is required to be moved.Ensures that Keff will remain<0.95 for all postulated accidents assuming NO soluble boron in the pool.B.ONLY one fuel assembly is required to be moved.Ensures that Keff will remain<0.95 for all postulated accidents assuming that the soluble boron in the pool is at the TS 3.7.17, Fuel StoragePoolBoron Concentration, minimum limit.C.TWO fuel assemblies are required to be moved.Ensures that Keff will remain<0.95 for all postulated accidents assuming NO soluble boron in the pool.D.TWO fuel assemblies are required to be moved.Ensures that Keff will remain<0.95 for all postulated accidents assuming that the soluble boron in the pool is at the TS 3.7.17, Fuel Storage Pool Boron Concentration, minimum limit.Confirm,..no bases is being provided to applicants.
 
FINAL RESOLUTION 5/30108: Comments incorporated.
 
Question is SAT.Page 30 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Q)ntent Raw s Q#1 LOK (F/H)2 3.Psychometric Raw s LaD (1-5)Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 87 F 2DDDDD DDDD u 038EA2.15 Modified 1.KIA does not match: question tests knowledge of purpose of the backfill method and ECA-3.1 entry point based on RCS pressure.This question does not test knowledge pertaining to the pressure at which to maintain the RCS during the S/G coold.own following a SGTR.2.Not SRO-only because the purpose of the SGTR cooldown methods is RO knowledge.
 
[reference generic KIA's for RO knowledge of EOP mitigation strategies (G2.4.6;RO IR=3.7)and RO knowledge of EOP bases (G2.4.18;RO IR=3.3)]3.Don't iterate on 3 items.Each distractor is iterating on 3 items: reason+stop criteria+procedure entry.Need to only iterate on 2 items.FINAL RESOLUTION 5/30108: Question re-worked to test that RCP#1 seal is limiting pressure for cooldown and also test basis for procedure actions.Additional examiners reasoned that depth of EOP basis knowledge makes this question SRO-only.Question is SAT.88 F 2 D D DDDDDDDD u 051AG2.2.44 New 1.1-AP-2.2, Fast Load Reduction, also includes attachment for estimating RCS boration flow rates during a load reduction; therefore,"0" is also correct because 1-AP-14 also allows use of 1-AP-2.2.Using AP-2.2 would not be wrong.FINAL RESOLUTION 5/30108: Re-worded distractors to eliminate"0" as partially correct.Question is SAT.Page 31 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial Focus 4.Job Content Raw sLink 5.Other SRO Only 6 U/E/S 89 H 2 DDDDDDDD D u 056AG2.2.36 New 1.KIA does not match because LOOP is not being tested.2.Do not provide bases because this makes both parts of each choice a"direct lookup." Suggest adding the following information to the stem: (comment may not apply if KIA not met)The vital AC bus has been transferred to its alternate supply.Which ONE of the following identifies the minimum tech spec LCOs that contain required actions for these plant conditions, including the required compensatory measures in accordance with the tech spec bases?[Provide Tech Spec 3.8.7&3.8.9 to applicant but NOT bases]A.TS 3.8.7, Inverters-Operating, required to be entered;TS 3.8.9, Distribution Systems-Operating, NOT required to be entered Concurrent planned EDG maintenance is NOT allowed B.TS 3.8.9, Distribution Systems-Operating, required to be entered;TS 3.8.7 NOT required to be entered.Concurrent planned EDG"maintenance can be performed C.BOTH TS 3.8.7 and TS 3.8.9 are required to be entered Concurrent planned EDG maintenance can be performed D.BOTH TS 3.8.7 and TS 3.8.9 are required to be entered Concurrent planned EDG maintenance is NOT allowed FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.90 H 3DDDDDDD DDD D S 059G2.1.23 Modified SRO only because this is a branch decision point (deep within an EOP contingency)
that requires knowledge of the procedure content/strategy in order to select the correct answer, Le., assessment of plant conditions and procedure selection (1 OCFR55.43(b
)(5>>).Page 32 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s 5.Other 6 U/EIS SRO Only Q=KIAwardLink 3.Psychometric Raw s Stem Partial Focus 2 LOD (1-5)1 LOK (F/H)Q#91 F 2 D D DDD D D DDD E 061AA2.04 New 1.Rod unlatching may continue without interruption (spelling)
is not plausible because it implies that they never stopped the unlatching even when the alarm came in.The stem already states that HP confirmed rad levels on the refueling deck normal...this implies that the activity was stopped;therefore, not plausible to say unlatching may continue without interruption.
 
See suggested wording below.l 2.Why is control room bottled air dump plausible in"C" and"D?" (no markup material provided to show plausibility
&plausibility analysis doesn't state why this is plausible)
Does manipulator crane rad monitor feed into control room hvac isolation logic?Suggest the following:
Which ONE of the following predicts the impact of the manipulator crane rad monitor pegging high and also identifies whether core alterations may conitinue with the rad monitor inoperable?
A.Containment Ventilation Isolation Core alterations may continue with the rad monitor inoperable.
 
Continuous HP coverage is required.B.Containment Ventilation Isolation Core alterations may NOT continue with the rad monitor inoperable C.Some other plausible actuation.(or explain why control room bottle dump is plausible)
Core alterations may continue with the rad monitor inoperable.
 
Continuous HP coverage is required.D.Some other plausible actuation.(or explain why control room bottle dump is plausible)
Core alterations may NOT continue with the rad monitor inoperable.
 
FINAL RESOLUTION 5/30/08: Explanation provided by licensee.Comments incorporated.
 
Question is SAT.92 H 3DDDDD D D D D E 062AA2.05 New Enhancement 1.The question is disjointed because it is asking for a procedure action and a tech spec basis (vs a tech spec and a tech spec bases).For example, test the 1 hour SW Tech Spec to throttle flow to the CC Hx&the bases for that action.This will allow for KIA match and resolve disjointedness.
 
2.The last bullet appears to have a typo?Should it be 2-SW-P-2B?(instead of 2-SW-P-1 B)FINAL RESOLUTION 5/30/08: Re-worked question to test tech spec and basis.Question is SAT.Page 33 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LaD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/6'S 93 H 2 D D DDD o D D DDD S we13EG2.4.20 New SRO-only because of"A" and"D." SRO must know that H.2 sends you to H.3 in order to get the correct answer.(RO knowledge can be used to eliminate"B" and"C" due to"B" SG level being high and potentially filling the main steam lines.Consequently, the applicant may be able to identify that dumping steam is not a good thing because of water in the steam lines.)94 G2.1.4 New HDD D DDDD D D u 1.LOD=1 because this question does not discriminate at the appropriate level.2.It can be argued that the first part of all four choices is saying the same thing.In other words,"Action must be taken to ensure the RO is replaced wll 2 hrs" Is the same thing as"Action must be initiated wll 2 hrs to find a replacement for the RO." Consider replacing the 1 st part of"C" and"0" with 1 hour(vs 2 hours)3."B" and"0" are not plausible because the stem data for operator B identifies 12 hours in the preceding quarter.Blend time in work control/tagging arena for both operators and get rid of the December hours.4.The third bullet is not necessary information in the stem of the question because of the 5th bullet saying that someone must be called in.5.Potential to re-work question to ask for reportability requirements due to individual being transported to offsite hospital.Gust an idea)We can provide a question if needed.FINAL RESOLUTION 5/30108: Eliminated vague wording and added changes to work histories.
 
Question is SAT.Page 34 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/EIS 95 G2.1.6 New F 2DDDDDDDDDDD E Enhancement 1.Use past tense in the bullets Suggest the following:
Given these plant conditions, which ONE of the following will be the EOP"Reader" and also identifies the EOP f10wpath upon exiting....?" a.Shift Manager Return to E-O b.Shift Manager Go to E-1 c.Unit 2 Unit Supervisor Return to E-O d.Unit 2 Unit Supervisor Go to E-1 FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.96 G2.2.11 New F 2DDDDDDDDD D E Enhancement 1.There is a possibility that choices"A" and"B" can be argued as correct if the clearance process is governing the alarm disablement.
 
Additionally, if the alarm problem can be addressed using another admin process (other than the temp mod process), then the question may not be hitting the KIA.3.What is FSRC?What is SNSOC?Will applicants recognize these?If not, define acronyms in the 4.Is there site specific Ops guidance on disabling alarms?Please provide reference.
 
FINAL RESOLUTION 5/30/08: Verified that alarm was multi-input alleviate admin processes creating two correct answers.Question is SAT.Page 35 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 97 H 3 DDDDDDDDDD E G2.2.35 New Enhancement 1.Define RCS temperature (2nd bullet)as Tave because it more closely mirrors the tech spec definitions of modes.2.Re-word the stem question: Which ONE of the following identifies (1)the OPERATIONAL MODE and (2)the requirements to enter the next higher mode?A.Mode 3 Change to Mode 2 may be performed provided the Tech Spec 3.8.1, AC Sources-Operating, action statements for the1H EDG inoperability are satisfied.
 
No risk evaluation and NRC approval is required.B.Mode 3 Change to Mode 2 may NOT be performed without a risk evaluation and NRC approval.C.Mode 4 Change to Mode 3 may be performed provided the Tech Spec 3.8.1, AC Sources-Operating, action statements for the1H EDG inoperability are satisfied.
 
No risk evaluation and NRC approval is required.D.Mode 4 Change to Mode 3 may NOT be performed without a risk evaluation and NRC approval.FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.98 G2.3.6 New F 3 D D DDDDDDD E Enhancement 1.Consider using 0.1 rem for"C" and"D." The plausibility explanation for 2.5 rem (i.e., 10%of 50.67 AST limit)does not appear to be credible.0.1 rem is justified with 10CFR.2.If at North Anna, the Chemistry and Health Physics groups are in the same work organization, then the applicant may be able to argue that Chemistry and Health Physics groups are synonomous because they are in the same work organization, i.e.,"B" is also correct answer.To ensure that there is not an alternate correct answer, we want to make sure that chemistry personnel are prohibited from initiating a release request.3.Re-word the stem question as follows: Which ONE of the following describes the release permit approval process in accordance with 0-OP-23.2, Waste Gas Decay Tanks&Waste Gas Diaphram Compressors, AND also identifies the tech spec bases for the maximum radioactivity content in each gas storage tank?(Note: This question is not disjointed-as previously noted in question#92-because this procedure action has a bases described in tech specs.)FINAL RESOLUTION 5/30/08: Comments incorporated.
 
Question is SAT.Page 36 of 37 ES-401, Rev.9 Written Examination Review Worksheet Form ES-401-9 4.Job Content Raw s Q#1 LOK (F/H)2 LOD (1-5)3.Psychometric Raw s Stem Partial FocusLinkward 5.Other Q=SRO KIA Only 6 U/E/S 99 H 2DDDD DDD oDD u G2.4.27 New 1.Because of the word"MAY", choices"B" and"0" are partially correct.How can it be completely wrong?Always use terminology of what is REQUIRED.Suggest iterating on whether Alert or UE is required.(withoutreference provided).
 
2.Need to re-word the choices like this: a.The safe shutdown function of"reactor heat removal" required to reach Mode 4 is affected by this fire.FINAL RESOLUTION 5/30/08: Tested procedure requirements (vs"may be implemented").
Changed the wording to clarify choices.Question is SAT.(laO)H G2.4.6 New 3DDDDDDD D D E Meets SRO-only criteria because 1 OCFR55.43(b
)(5): assessment of plant conditions and procedure selection; must have knowledge of procedure's content in order to select the correct answer.Enhancement 1.The stem needs to further define bullet#7 ("crew is performing ES-1.3")because if the applicant assumes that step 8 has been completed, then"A" becomes the correct answer.2.Are the applicants expected to know what"step 8" means?Do we need to further define?3.Does the control room indication for containment pressure read out in psia?Psig?Ensure that the stem of the question provides the same units as the control room indicator(s).
 
4.Re-word the choices: Given these plant conditions, which ONE of the following describes the hierarchy of required procedure actions?A.Immediately transition to 1-FR-P.1, Response to Imminent Pressurized Thermal Shock Perform the actions of 1-FR-P.1 to stop the RCS cooldown and then return to 1-ES-1.3 B.Immediately transition to 1-FR-P.1, Response to Imminent Pressurized Thermal Shock Verify that RCS pressure is below the NOT setpoint limit and then return to 1-ES-1.3 C.Remain in1-ES-1.3 until transfer to cold leg recirculation is complete through step 8 Transition to 1-FR-P.1 and perform the actions to stop the RCS cooldown and then return to 1-ES-1.3 D.Remain in 1-ES-1.3 until transfer to cold leg recirculation is complete through step 8 Transition to 1-FR-P.1 and verify that RCS pressure is below the NOT setpoint limit and then return to 1-ES-1.3 Ans: 0 FINAL RESOLUTION 5/30/08: Comments incorporated with minor adjustments.
 
Licensee concurred with step 8 being listed in"C" and"D." Question is SAT.Page 37 of 37 ES-403 Written Examination Grading Quality Checklist Form ES-403*1 Printed Name/Signature a b:&Iv NfAMIA"VI+1\\lA, mB'?!rJL N/A rrf;Date 7jz4/t;t.IlWi rz/e:Lf br trfIZG/o!Date of Exam: Su-ll\eExam Level: R Item Descri tion a.Grader c.NRC Chief Examiner (*)b.Facility Reviewer(*)
5.All other failing examinations checked to ensure that grades are*ustified Facili: North AV\vttL 3.Applicants'
scores checked for addition errors reviewers s at check>25&deg;A>of examinations 6.Performance on missed questions checked for training deficiencies and wording problems;evaluate validity of uestions missed b half or more of the a licants 4.Grading for all borderline cases (80+/-2&deg;A>overall and 70 or 80, as a licable,+/-4&deg;A>on the SRO-onl reviewed in detail 1.2.Answer key changes and question deletions justified and documented d.NRC Supervisor (*)(*)The facility reviewer's signature is not applicable for examinations graded by the NRC;two inde endent NRC reviews are re uired.ES-403, Page 6 of 6 ES-501 Post-Examination Check Sheet Form ES-501-1 Post-Examination Check Sheet Facility:
Date of Examination:
:r w1e 2..Dog Task Description Date Complete 1.Facility written exam comments or graded exams received 7/3/0S and verified complete 2.Facility written exam comments reviewed and incorporated 7/Z3/()g and NRC grading completed, if necessary 3.Operating tests graded by NRC examiners 1/;JJt I t:J f;4.NRC chief examiner review of operating test and written exam grading completed 5.Responsible supervisor review completedI'd-?{J IJ g 6.Management (licensing official)review completed 7.License and denial letters mailed'ii/I/f)8 8.Facility notified of results'7/Z;109 9.Examination report issued (refer to NRC MC 0612)3/S/(J'g 10.Reference material returned after final resolution of any appeals$j/$/O!J VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 12, 20()8 Mr.Luis A.Reyes Regional Administrator United States Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St.,SW,Suite 23T85 Atlanta, Georgia 30303
 
==Dear Mr.Reyes:==
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 SUBMITTAL OF FINAL LICENSE EXAMINATION WRITTEN AND OPERATING TEST Serial No.08-00540 NAPS/JHL Docket Nos.50-338 50-339 License Nos.NPF-4 NPF-7 This letter is to inform you that the final copies of the NRC License Examination Operating Tests were sent to Mr.M.ark on May 23,2008.The final Written Test was hand delivered to Mr.Mark Bates (NRC)on June 6,2008.This information supports the administration of the licensing operating examination during the weeks of June 2 and June 16, 2008, and the administration of the written examination on June 24, 2008.If there are any questions concerning this material, please contact Mr.Walter Shura at the North Anna Training Center, (540)894-2479.Very truly yours, Daniel G.Stoddard, P.E.Site Vice President Commitments made in this letter: None.
 
cc: Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20005 Mr.Malcolm Widmann, Chief.Operator Licensing and Human Performance Branch Division of Reactor Safety Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Mr.Mark Bates, Chief Examiner Operator Licensing and Human Performance Branch Division of Reactor Safety Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 NRC Senior Resident Inspector North Anna Power Station
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Latest revision as of 14:37, 14 November 2019

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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