ML022970052
| ML022970052 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 05/14/2002 |
| From: | Vonsuskil J Exelon Generation Co, Exelon Nuclear |
| To: | Dyer J NRC/RGN-III |
| References | |
| 50-456/02301, 50-457/02301, BW020042 | |
| Download: ML022970052 (132) | |
Text
INITIAL SUBMITTAL OF THE WRITTEN EXAMINATION FOR THE BRAIDWOOD INITIAL EXAMINATION - JULY 2002
Exeik,~,n Nuclear May 14, 2002 BW020042 James E. Dyer Regional Administrator U.S. NRC Region IlIl Administrator 801 Warrenville Road Lisle, IL 60532-4351 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50-457
Subject:
Submittal of Integrated Initial License Training Examination Materials Enclosed are the examination materials, which Braidwood Station is submitting in support of the Initial License Examination scheduled for the weeks of July 8, 2002 through July 19, 2002, at the Braidwood Station.
This submittal includes the Senior Reactor Operator and Reactor Operator Written Examinations, Job Performance Measures, and Integrated Plant Operation Scenario Guides.
These examination materials have been developed in accordance with NUREG-1021, 'Operator Licensing Examination Standards," Revision 8, Supplement 1. Please note that reference materials are attached to each individual examination question or item.
Some minor modifications have been made to the Integrated Examination Outline with regards to the operational scenarios in order to improve balance and content. These changes improve examination quality and are in compliance with NUREG-1021, Revision 8, Supplement 1.
Some modifications or adjustments to the examination material may be required due to procedural changes.
In accordance with NUREG 1021, Revision 8, Supplement 1, Section ES-201, "Initial Operator Licensing Examination Process," please ensure that these materials are withheld from public disclosure until after the examinations are complete.
May 14, 2001 U S Nuclear Regulatory Commission Page 2 Should you have any questions concerning this letter, please contact Amy Ferko, Regulatory Assurance Manager, at 815-417-2699. For questions concerning examination materials, please contact Mark Olson at 815-458-7856 or 815-458-7829.
Respectfully, Ja s D. von Suskil Site Vice President Braidwood Station
Enclosures:
(Hand delivered to Mike Bielby, Chief Examiner, NRC Region l1l)
RO/SRO Composite Examination with references attached Control Room Systems and Facility Walk-Through Job Performance Measures with references attached Administrative Topic Job Performance Measures with references attached Integrated Plant Operation Scenario Guides Completed Checklists:
Operating Test Quality Checklist (Form ES-301-3)
Simulator Scenario Quality Checklist (Form ES-301-4)
Competencies Checklist (Form ES-301-6)
Written Exam Quality Checklist (Form ES-401-7)
Examination Security Agreements (Form ES-201-3)
Record of Rejected KAs (Form ES 401-10)
RO SkvScraDer I SRO Skvscraw I RO SvstenVEvolution List SRO Systemn/Evolution List Outline Changes Question Topic ( -itimjous Ror1,fhA,%al Dunriq r-%or r n - d, I !I in \T o. S r ttiaticri or) r I V'jii h t I'.l f lo.%. os,;REO(iRED o i giq; the PREFE RRED ioth: (t f i; ir 5 ! 2rsllorl t, IiV evit)?
- a. (I:
) -r 1( \Q i-l start the BA tr~iws-t r puirt) (fi A f!.Ti
'V.tIr y borisiooi flovw >31, (;prn ll, f r*.l ill); . -
- b. ();-,I I?1 12D or 1CV1 12E ( or 1CV1e 1Vl12B l(.V1 12( msi~,ri /e (Jiarqiilt oN isclti Itwin
- c. Ocen 1CVi '-A and 1CV1 10B start the BA transfer primp verify cli r(piq flow -30 gpm
'd. Open 1Sl8801Aor 1SI8801B. locallythrottlerunningCVpumpdischargevalveto match IFI-917 and ee own flov Answer a Exam Level B Cognitive Level Memory j Facility: Braidwood ExamDate: 7/19/02 KA 5000001A104 AA1 04 ROValue: 38 SRO Value: 36' Section: EPE ROGroup: 21 SRO Group: 1 System/Evolution Title j Continuous Rod Withdrawal LJ Statement: [Ability to operate and / or monitor the following as they apply tc Continuous Rod Withdrawal Operating switch for emergency boration motor-operated valve operating switch Eapanation of (Al is the preferred method (listed first) per 1BwFR-S 1 ( B and C) are backup methods listed in FR-S 1 f (A) is unsuccessful. (D) is I
lAnswers:
only an opbon listed in OA PRI-2 _, _ait
_ _ - == ________ _ __ _ =_
ReferenceTitle FacilityReference Number Reference Section PageNo. Revilon L.O. Number i Functional Restoration - ATWS Procedure I 1BwFR-S 1 Step 4 4 1 AWOG !F ii _ . - _ _ _ _ - -
F1ajt rial Required for Examination l _
Question Source: New =ustlonModification Methiod i Used During Training Program Question Source Comments Comment Type Comment _Reviews j Complete Peer Supervisory Facility NRC I
RO SkvScraoer I SRO Skvscraper R0 SnsternlEvohition List lSRO SvstemEvolution Lit Outline Chances l l Question Topic Dropped Cri(rol Rod The foil. .i:,,; pln ,1 l n (jo1t
- Ria, t,, plo er ,5 r iT,, *ISir F Pr' r.i posr~r i 2225 p; I; Rod H 8 .'rops to tte bottom (f the core
- ROD AT BOTTOM ,i'irirr its IS LIT Ire It. 'A ,Il.rlr i i r p irit 'esp : '. t. Ii';
i erutIS , S ';orr. 1 C TRi.e *2i i 1: 12 a, 2i-i,~
n rj~
b .D ro, isis Ilrireis,'-
- c. Iir:reaiss Decreriises
- d. Decreases Decreases l Answer d Exam-- Level B _
__Cogniive Level *..
Comprehension
. 1.Facility: Braidwood J ExamDate: 7 19/021 KA: 100003A106 1 06 ROValue 40 Valuecn EPE ROGroup: 2 SRO Group j Systerm/Evolution Title Dropped Control Rod
_Statemeint: [Ability to operate and / or monitor the following as they apply to Dropped Control Rod j 1RCS pressure and temperature ibnation of [RCS temperature and pressure will decrease with power immediately following a dropped control rod ID) is Correct Reference Title [ Facility Reference Number !Reference Section Page No. Revision LO. Number I[Dropped or Misaligned Rod jp1BwOAROD-3 llSymptoms 101 - --
lBwOA ROD-3Lesson Plan Iri1--oX-XIL-34 l' = [ 8 2.5 Materlal Required for Examination i _ _ l Question Source: New j Question Modification Method: j fUse During Training Program Question Source Comments i Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic If I;,.- it,,. (,- t', R;:
j, ,. , ple
,, , ;1i
.s ,I
' i . II), '- I '.'
a.
b.
C.
- d. .
Answer b Exam Level B Cognitive Level Application Facility: . Braidwooc ExamDate: 7119.02 KA:! OOOOOSK 101 AKI 01 ROValue: 3 1 SRO Value: j38 Section: .EPE ROGroup: 1i SRO Group:
System/Evolution Title Inoperable:Stuck Control Rod 005 KA Statement: lKnowledge of the operational Implications of the follewirng concepts as they apply to Inoperacle Stuck (lontrolRod 1 Axial power imbalance
!Explanation of l Per 3 2 4 - reduce power greater than or equal to 3% for each 1% over 1 00 OPTR will be measured Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and "Inewers: thermal power reduced within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of each determination (A) is incorrect - the TS is not applicable telow 50% power (C&D) are f
- _ - _ _ ____ _" ___.J*_
Reference Title Facility Reference Number Reference Section Page No. Revision! L.O. Number Dropped or Misatigned Rod 1BwOA Rod-3 8.9 101 j Tech Specs 3 2 .1 324.1 110
.Material Required for Examination I _---_
i iQuestion Source: Facility Exam Bank Question Modification Method: ! Editorially Modified Used During Training Program Question Source Comments Comment Type Comment Reviews Complete
.I Peer Supervisory Facility NRC 3
Question Topic _ i. :
An,~ ! , . fI, : ,; '~i I, ;I;. r ,;-i~, ' . I . r 1, . :.... l.i*l.t r" .:wct@
l' bp'.' .I' ' r r ' X ! 1' . i ;-,,
- a. 0 ,f II I 'i-bC . .,, r, o 'Il I. i, 1 Answer a Exam Level B Cognitive Level .Memory Facility: Braidwoodj ExamDate: 7 19 02 KA: 000007K203 E-2 03 RO Value: 35 SRO Value: 36 Section: EPE RO Group: 2I SRO Group: 1 21 SystemlEvolution Title R.-,i(:tor Tr.p 007 KA Statement: Krnowiede o' theinterrelatiors between Rea( tor Trip arid the followsing Reactor trp status panel Explanation of (Per 1BNEP-0 Step 1. actions are closed bulletted therefore reactor trip breakers must be verif;ed ope n or the RNO applied to Answers: l manually tri, the reactor After the manual trip attempt the operators may proceed to step 2 iB incorrect I Transition to FR-S 1 is not
-'-I ' ; ^ ^;;';'^^*'-s---;.,
the status of Reactor Trip Breakers while performing the RNO of step 1 (C incorrect)
Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Reactor Trip or Safety Inlectorn 1BwEP-0 Step 1 1 3 100WO Material Required for Examination -- -- - - J Question Source: Facility Exam Bank Question Modification Method: lEditorially Modified 1 Used During Training Program i Question Source Comments 1997 Bwd NRC Exar.
Comment Type Comment Reviews Complete Peer I Supervisory Facility NRC
RO SkvScraper SRO Skvscrap~er RO Sysem/Evolution List SRO Systemr/Evolution List Outline Chancies Question Topic Fr., '*. ~ ~ , r. . i ~ ' .i It
- I, rI r i' rr li, ?I I
- /-i rri T it.
- a. .. [4 Bi.rr F f oV. Ar- :. ( ,.
- b. 1r TI I ,R L)E [~.F 3 - R t: i rir 1 i. ~ S it 1ri'rrd C(>i.
- c. DE(~,RA[)F[) 'B,,FRC e:r' tn) Do'i;r~itedt Core.Lr)rr
- d. INADEO.UATE l BwF R-( 1, Res~ponse troIradeqriate Cure Coolinrj Answer c Exam Level 'S Cognitive Level Coirnp'ehrersiorr Facility: Brar !,.rrri ExamDate: 71 9,02!
KA: 000008A216 AA2 16 RO Value: 38 SRO Value:. 41 Section:I EPE RO Group: 2~ SRO Group:'[ 2]
'Syv,ten-JEvolution Title Pressurizer Vapor Space Accident 008 KA Statement: Ability to determine and interpret thre following as they apply to PreSSUrizer Vapor Space Accidernt RCS in-core thermocouple indicators. Use Of plant coniputer for interpretation -
Explanation of (C) Correct - given conditions present an ORANGE pith orn statuS trees At >700 F ttrc correct printsedurre is, BwFR-C 2 (A&Bl Answers: are Inco r rect as, the ORANGE path Overrides thre noirn il EOP are a Yell ow terrninr no C D Incorrnect 1200 F required for this Reference Title Facility Reference Number Reference Section Page No.' Revision 10O Number Status Trees 1BwST 2..VWOGi1 Material Required for Examination 1B-.ST-2 status tree & Steamn Tables Question Source: .Facility Exam Bank Question Modification Method: ~Editorrally Modifier: Used During Training Program Question Source Comments 2001 B,,dc NR(;
Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic . ... '.
I .,, t * , ,, .
C j. . : , .t Answer ; Exam Level S Cognitive Level Applio Facility: . . ExamDate: " i' KA '000( &,j( 2 4 .o RO Value: 22 SRO Value: .3 6 Section: RO Group: 2. SRO Group:
Systemn/Evolution Title Prot-..-irizer Viqour S;~,i A( ~:0ran 00)8 KA Statement:
a.l ,of wti,! rts eb to .' operati:i'y, . , b d to, Explanation of Per TS 5 6 4 - Monthly O)peratimr; Reports Documnent Answers: ali clallenr(;es to the Pz-r PORVs, or Sift~ty as the PORVs were chjllenged ad is also reportable (iiA) is correct (B Incorrect
'C&D' Incorrect . it is reportable
-Reference Title Facility Reference Number Reference Section Tech Srpecs . M1onthly .
Page No. Revision' L.O. Number
,Iti
. ti.. R,,1 ' 5 6 .4
- 56. 2 A98 Material Required for Examination Question Source: New Question Modification Method:
Used During Training Program Question Source Comments Comment Type Comment o1 Complete Peer Supervisory Facility NRC (I
Question Topic " '
C
.1 ,,
I' , ': ' ,
p; , . ,,
a-. r
.1. , ' ,;
- d. . * ,. , .. :. .! : ' h 4 ,,-r, ' '
'! 4,4
- . gj :f .
t? 'P.1? 1i ' .41 .
- .', , . * ,4 f , .
Jr 'I'te Answer .i Exam Level B Cognitive Level .1JFliry Facility: r . ExamDate: 7 102 KA: ! K1)1 EKI (1 ROValue: 12 SRO Value: *i7 Section: Pt ROGroup: 2j SROGroup: 2 System/Evolution Title Snmall Brei.. I G(rp : 2 S KA Statement: FKnovw.f'(!( f of tie optr.ii;rr iS I.l'i-ril:. 2 0St Ioloi'r :;
N~wllr~g (lr¢llllteol .rl( (:,(, ri;:I' 1,, ,i,onsoef t, ,,j (
I', ?.i , S .i 3 .il Lo(;
Explanation of (A) Correct - refltux cooln( InvolvrevoI Answers: t1owltC thes c ( t on of .Ktefr ' I.:'te<
'4 the Rx core via the hot leg Occurs, te 4 ;( ri.ors .r4 n irc?the 40restltant liquid abck atr r core ,. t409 srwiptin. n iatural (circu)Iltirorr 'ot fl._,
Reference Title Facility Reference Number Reference Section Page No.
Backgro III(1 Documrernlt -Revision L.O. Number E 1 Mvtiqae, ,; ('ore Darii2;i;, LC( 'I lt, 1 I,
I (O)(a , . ( 4444* 1-1."'i 10 Material Required for Examination Question Source: Facility Exam Baink Question Modification Method:
' Editcra.ily M. (dfmie1 Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC 1
RO SkyScraper SRO Skvscraper RO Svstem/Evolution List I SRO SvstemiEvolution List I Outline Chanqes I i-I Question Topic i . L 1 ..
a Ir , -..
b f :hh I C. *t ii : 1 .. *1 I
- d. P,,: c,1 j 1!1.'; ;1, .. ? ,. I is, Ti.. *t'i:cri ;he,.*$ ,0 a Answer n) Exam Level R Cognitive Level C omprehensci(l Facility: B~. cl .o( . ExamDate: ' 19302.
.KA: l000011A210 ~ EA2 10 ROValue: 45s SROValue: .1 7 Section: EF;F ROGroup: 2' SROGroup: '
SystemlEvolution Title Lair:;e Brej k LlILA 011 KA Statement: I Abilty in Thrte rrriiie aini1 re'bprret thel f Nll~irii as they apply t)i Laqi Break L()LA I
\/erificatioii of arlec<;urte, (. in coolinc; Explanation of l Rei n tiatori of Hg h Heae SI s the maost cliect ye method1 to reif avf ci The core a](rid s tor} aI : eqi ate ccoeb cool ng- 18 vF R C 1j Answers: I ba kgr~rnd doculment B iIS the correct re sponse Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Backqr (rlic Docrirerfts li.id.il .ite .i ir ; BBFR C. 1 2 1 Material Required for Examination Question Source: Ne(. Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment CReviews Complete Peer Supervisory Facility NRC
i/ I b
f-I.!f,
)..o"";
."It" o C . .. I _, "I, .
. ' , t .
C. I Co"d ,/
/ CfrCw
.J Afr -_--
(iQ 0 0 7 Co"ie
" s 'S:
(ewe/.
Of Li"}>e:E Paclit .
is* I...
&4!Xp, (f/f, Refee ri
-- 0 L°a,.> - - ' Go~
'ts- _ rF4 / S()°Groi,
.)Is sr' ,
Facility'&Ofe -- "'at IfjD ZIR,%
If t,
- -serr l -
0C
-, e e, I ' 'Z et'r sect ,,)C
.01) ,Jressco a24,
- .- f o pa "js
"'MfCat.
C/..4
'is,, o'"in r,.,.
ii0917 p'.~l
-_ __09a-f _*IIo -c
, , Wpe, s CO Fcility~
IVI?C q7
RO SkyScraper SRO Skyscraoer RO System/Evolution List SRO SvsterrmEvolution List Outline Chanqes Question Topic , ,; :.a ,.
. ,,, .1' - -,
.0
- a. 7t .I' ,!: r4 -, 'i .... I 1 s; P ...... I4 Answer Exam Level b Cognitive Level (>'r Fnli ii Facility: ,
Gr ExamDate: 7 '10 KA: B00()17A122 AA1 2. RO Value: 10 SRO Value: .1 2 Section: f P; RO Group: 1i SRO Group: I Systemf/Evolution Title Rcv (f ulPrnOirr:p lMat.nIt!,rs% t of R( f o, )17 KA Statement: ibty tO u;rnmn .1' no: nit tI *'C.wi r toy *9 ; 1 t . ii.orl Pnop Mitimi I u ' ss ot R(. flo' iW (-P stilfaili.......... tIt,),Ilfun b tlw)l................
Explanation of Ilficltiolsare tt).11 the No 1 soni ha', falet-d Tho, .;)fetor lt. 'nt
.t( lly )f 1Bw(AR(P. )A RP 1 st.a(es to) s)op12 Mich states t.
Answers: trip the reactor at I!f:ie R(.P DDue to Itt tl qir en. lninkofl FL.', c( nt new:ri m)ritorr,r,
- isno!t thre tnro;n
- nr in ItonI tO taikt A r-orrtrolled Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number RCP Sentl Fi.,lrr 1Bw iA R( P 1no; RCS LP AP-XL o1t R(.P S.,;d F.liture L[P )1 A XL- 27 : ' l Material Required for Examination Question Source: .nl Bu, ,ly Rink Question Modification Method: DLn. I h Soir t, Used During Training Program Question Source Comments ' tt..
4 NM[
Comment Type Comment Reviews Complete Peer Supervisory Facility NRC Ic
.over SRO Skyscraper RO SysterrdEvolution List SRO Svsterm/Evolution List Outline Changes Question Topic .
C. I ; . S t
,d. .T , .q :;-tL r.. . i ;t -t.. . I....
- b. R .
- d. .,I)R ( .P [, Ii Answer c Exam Level R Cognitive Level (Cofl.[1i'u'isfof Facility: 8raiidw~ood ExamDate: i KA, 060024A~i : AA2 A RO Value: 36 SRO Value: 37 Section:' EPE RO Group: SRO Group:
System/Evolution Title . (B4,t KA Statement: AtA',!I,,!- ,tI'Oin':e ui iniiterpi thiefollo',iring as they apply to Emergency Boratiorn
'Ex-planation of ()0 :(,IC116) i/sopen on loss of a~r.cooling off letdown flow At lower temlperatures. mixed beds haveathiogher affin~ity for
,Answers: borw I t Yro in ttw RCS causes power;RCS temperature to rise Control rods will step in (A) Incorrect -letdown tenipeiatiirt.
- d. .etdcovn t .i.- iwn pressure to rise
-Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Uncontrolled Dih-i- I wOA PRI. 12 - Symptoms istep 3 4 100 CVSL I-CV-XL-01 ll5a) 1) 1 aterial Required for ExaminationL7 Kestlon Source: Facli, y Exam B VQuestion Modification Method: 3 ect Foni Si- Used During Training Program estioneSourcetConTitleft . 20N, 1991 Zion NRC Examn Commn t Reviews Complete Peer Supervisory Facility NRC
RO SkvScrater SRO Skvscraper RO SvstemOE volution List Outline Changes Question Topic .
1T, . .. . . . .
- b. .. ; I . P. . I ;
C. I' ..... ).-. P;F I . I I . hit
,, ') ;,I . Ir
- d. i.-. ( )A 1lto) : ,? , - .T pl : ,! 1,1 l 3~ -p1, , i t,.
AnSwer A txarrI LIevei I ognhtive Level ")nit Facility: i' ExamDate: ' 1 0(2 KA: ')(!2?(;(i1l 2.14 RO Value: t (! SRO Value: .t Section: fPi RO Group: 1l SRO Group: t System/Evolution Title S IF . :7F)( y B!)rn.ev.r
(,, .,
KA Statement:
AtilIity tI nr ((;, ,zeibr rorit IT il i tIt) . for (oper, Ir(
nynteri t[.IIIr7?7Itr r, V. tII r en try It 1 I u(!tt n , s i1tor erynergremy andl Explanation of (A) (ct, t . P.. 'i-P.P o st) 1 N(I enter 1R?.%JR S 1 '.A,. vt11 APmt :07-'. Iii. In(rettrq(uny torrale (B) Inlnorre(t Answers: Thre ., , .ytttt)iint for
'or Pr' . t!). tI)! t :.i' .1 I's Ip1 1I.ti:h
. ', t No , '1. in '., of A in tin ttrjI itt (!Ilhtlt.'
t ~ .. ~ . : . , ;., '. ;
Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Abnornri( O)pe';it nq P r,, - 1BE3*.)A PR 2 PRI 12. Ro)D 1 B 12 '58 1 ( 5 Er1(rr(rqrn( y Optervigin; Pr ), ("1-' ' B.&f P 1) S'ep 1 Fin(:tion.i t.~ll]ir: P~ t- -, B1 F3,;F R S t Sttlp .1 l 1A Material Required for Examination Question Source: r.i . Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete ISRI A- It'r- ' - 1!.1 + I 1o f 1 j1 f po~it"' r - ....... Peer Supervisory Facility NRC 1I-
Quest~ori Topic . . s
- a. . . .. ..
b . r I , * . ;
Answer Exam L,evel f Cognitive Level m.t. ri,- Facility: .. i ExamDate: I 1 It KA: ( )0o,:K I AK 1 ()4 RO Value: . SRO Value: Section: f P[ RO Group: 1 SROGroup: I System/Evolution Title r Ir;i ri yfi,,It i i;r, KA Statement: KrizA F; (if tlIrl,( .t l l, ", 11 11.1I ftfw ,' -i;1 iii i i;y ! I
..s t t : 'q'rt~ ir e ur n? . fi ~Fiiir sl , . ,,r ,, ,
Explanation of ; (Ccrr t- TRNI rrjl uir.-n *. , 7 'f' ;):in. w(t wf i , f A i r I i jrl f In r(
nmrrn in.irv-H1 i . I for flii'& )I?'I i)n.l,( s Answers: 12D&.L wun:d 1(,V81nI Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Reactivity (Curt o'f k .1 . ' t .' 1 Material Required for Examination I Question Source: .: Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
RO SkvScrarer SRO SkvscraDer RO Svsteni'Evolution List SRO SvsteriEvolution List Outline Changes Question Topic : - .i I ..
i'"". !' .. - .r' Answer ': cxam Level D Lognirive Level 11;;,I Facility: Hi w!.. ExamDate: .7 1 (.1 KA: 0(o'(25K2()1 A o..
(i RO Value: 2, SRO Value: 2 Section: f f'f RO Group: 2. SRO Group: 2.
SystemlEvolution Title . t ' R-,1,-. IF1.iI W., '.1 S,.t1.' :25 KA Statement: Kiole edge .fI tMnrirnlrrrl,til i , ht.s ri Lo-. oi fr i..1jA.i
.i H(iJt R-iuoval Syi. ! .- II' (! '. , 1(:.vnq Service w.vlt r or c1,owrei (* )ol r~qv'All' pwniir;>.
Explanation of ' i (;orre- . i. 1; TWiF.(1,1I II:. . iiu(ru I t , Ill i i 1.v t .. .
iiliiI .i , 19 iol*, '1 vt .19 )yli..s WeuRH H eia Answers: F . h r S-r .r RC fitS,..thr2Mi ?'
,R(S .i', uliri-j.r.' Id ..- .rie RCS , uu. i I w,' lilt r .r. toe (C( '. .11r Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number
- Norrrili (O)Firlting Ptr iciu ijr,
- i( m; B6.r ):' f)f 1 *. F 1. ' ': . 26 B.(! B3iq Noliu. HF11 . 1 .1 Material Required for Examination Question Source: Ni.'. Question Modification Method: i Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
RO SkvScrapter SRO Skvscraoer l RO SystemlEvolution List SRO SystemfEvolution List Outline Chanaes
- I Question Topic . .
r ., ..
- I, ,; "- ' '
.'. , , ;' , '. 2 ,'j. :'j.
- a. r' 1 I,
, i?.*- . ., ~; '1 i1 i t1, i . . i ! t ?Iirr: , ! ,..-
- b. ;P . -~ h- P. ,, . -.r1 I
.s urr d t-i !t- i 1)i I hlI l .
C. V~'iri II;,i I Idvr "II ;i. r %.r FBEWEF'
- d. St~irt ,ilit~ I("F . V , jrin:,. fAl,, . - 1:, , I. r ,.', (!- t1., ;h tHe F ( .A> + . t IE v; , r( . Ir u ( ( .' t.irIs, I r rtI di s 19 Answer I, Exam Level S Cognitive Level ( 'ripretif)t . ,n 1 Facility: I Braidv.r>od r I ExamDate: 7 02j KA. 0('f) (A2r .1 AA, 'A RO Value: 2 SRO Value: 2 9' Section: FPE RO Group: 1i SRO Group: i 1 System/Evolution Title I , .1f scrp. rent ( Co~, rr il * (i.t; K(A Statement: Ablrirty, !t ... .mr irv! nrttrr:r r, sI rr..rrrs; vit', it,: . I. I r(,- .I (r"oiiitrsini ( sdo irsj T1it r r, rrI,, . II . ' i ~
r : :s r
! IIi In I I. r lt r It -r i , II IIT I t t, ( ~I IIr I. , I~ -r t -. r(;I (l tI t 'is,_' ..' :
Explanation of AI'rr
, rtr i - P( 1)1, 1' I r; l i i' it i .i'i *.. N t I ir r no, 2 rl rr . ri tIii . P, F . - ~ ~II r r ,i I , e i i r ; . 22 Se a l our le t 2 .~5 F ifir ,r~rest t er 1B MY)A P FRI 6i it~
h ,I,,Srt oil r i: Irdii (I nr: terri;s, III il~irii he~it ex Ahiiirpr ouihl Nill be . 1/2O F Answers:
t t ' l I~,? w,. ii ( A [lirt o rrirrrriq iD i In tI-rs ~ i;. (.( 1I-s throt ri;h I rri iwii ~ ,h m tr %llo l o l c (~
n1h .. R 1 5 r ,r,Il-:-...r c w ir a~ry to Sir t ,r)ri. ni-r;iruiiI i ( )A P R-' I Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number (o mpo;nriiur t (:)o'rr 'i; .l. fim i t,I, 1, N.( A tP'R *, ?At.1i Bodly r'r 7 I 1()
Annuni ati(,r Rwp ,,,.. P~sio l - . 1 2 (.'rC[)' 1 . -Ei.sE5. ( siuse A, t l ,1 Ir j Tech,',:+ [.a'.i" Z Li Material Required for Examination Question Source: N . .. Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete P I1 I . ! -;I ,t ! I. I I '- I , t '. t I I I . i'. . I '. ; Peer Supervisory Facility NRC
Question Topic;.
- *I. ,.>, .' , '44b..
,,,.,, I ! 1 .
'I.. 1l ~ 1'!
, "-~;,(I 4, it -' : ." tII .1 ,
1(, ,, 14! ,.,'o: .' ,'! . ' .J,' .
- d. l B:.(.r, i , I:
,I .I t.), fil sl:.
- ., - t
- I~~! fr .,I,
,,' .Tt Ir I,;
Facility: F3%i.A- ExamDate: 7.1( 02 Answer ( Exam Level S Cognitive Level A p) : i ,', M" RO Value: t 1* SRO Value: I1 Section: f Pi RO Group: 1 SRO Group:
KA: (i9'(Yi02( ;I '.1
( rii nit (:'1) a .' (26C SystemlEvolution Title t o", ofi (!t r; rip KA Statement:
is i( n,: Iw,!, sIt l -r,.it n :1.! 1 t r.i,w -, ., 1,
- ,-,m It. i,t il-)vr-1tt !1il r.tt -r . (;t -rir(y1m A~t;it,t ,,I rht o,3 J 1t ,leer Explanation of rT. ( (n,. irlll]er:ff'l ttf(
tit1 : rf ,j,' Xi.
,o,.t':.d t.',-.oi!t;,IfR
- i. ..........................
Answers:
r[:1 ,r ' f((S pr, '.f :s,sr, I . 4rl ,i6 1'i- ' t,,
Facility Reference Number Reference Section Page No. Revision L.O. Number Reference Title Atts ,,," iret A I* a, ( ,
(;(,ii;. ;)i1 1t Co oh r ifIjf1. I1,) ] I1B .'PIt ,r ;,
A n ii' i o w R i-.Ii " ;i' ' fi,^Ai; I ,' al A--S :
Material Required for Examination Question Modification Method: Used During Training Program Question Source: N Question Source Comments Reviews Complete Comment Type Comment Peer Supervisory Facility NRC
Quesuion Topic . ...
, ".. ;'l.
Answer n Exam Level H Cognitive Level : 1.1iri Facility: -ri
.,1 ExamDate: ; 1'2 KA: ' 1U'K2 1' RO Value: . SRO Value: , Section: fPr RO Group: 1 SRO Group: 21 System/Evolution Title b....,.r..., .I , I ., I M :,i,,r
1,F . .r .c 't-,.t.rt- (( 'ctr(ol r.ihiltlcncticon L~l~ewf tw#l (,8 of 1pw(1,',t,o ...
I-...t ,.......
Explanation of (s\l (A(r)cc.t - Icicl r.,... ci c. .rc rll.c.rc.q 1c'l tit P. .i. FR(,S hftc,.i- cip irnld'.1).rcI'. wlc.cr(;. IcV rrcpr'-.'ses tthe Pzr titjblce Answers: ril..irnq fre .t.ir 1,:.;h:.
c it,:..,c,,'c Ic crct'rc'..t1
) rl .,M,r. b:h c(:. !, ro chltttI, )f- r'.` EV.ri ricorrc-t .sleI Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number crcr')I r II . ' X l .. .. .). . ' 2i '3 Material Required for Examination Question Source: N.. Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC 1i
R0 SvstemlEvolution List SRO Svstemfivolution List Outline Chancies R0 SkvScraper SRO SkyscraDer Question Topic ,
a : I..
Ic I, t- itt ; 1, !t ;!...I; ,J 1, . 11. I it-o.......... .
d.
ExamDate: 7 1 02 Exam Level Cognitive Level !.' '.'. Facility: b.
Answer c
- 3 System/Evolution Title * ,1 ,n Abtity i tprrt II !,lo r . III, .* .' 41,fll.1; KA Statement: t s)ff 4 7 ,,f **sr. l) lb *.s it t.c't I1-IiK If 1 the (flld S drf)op)e(d Explanation of P'er TRf 3 if i , U 1I 1 '4 , I ,vf lf .th 1,,
ifl [)S.it)li ,I1 te ft of ,r twl ir itile rfcks vvill riot r . il I' I ilt- to WX1 )W r.wfrrt I" I I I ' ,j1 3/4rfflt)[y Answers: jtwi ct'i'tw i, Reference Section Page No. Revision L.O. Number Reference Title Facility Reference Number Rrt.f q I,():Srtil [; - RM.
(4 Ai'.
b3,i<
TS iold)
Material Required for Examination Question Modification Method: Used During Training Program Question Source: N. .
Question Source Comments Reviews Complete Comment Type Comment Peer
'.'t! )T ', i :'.1'.
Supervisory Facility NRC
Question Topic . . . :
.'. ' , I . - * . , . .' . 1. , I
- a. ' ;I : .. :.
b, : ,,, . ! -. , ' ;'
- c. !, , .I . , .. I r, . , " , !I
- d. I :§,.1 r- ... , , . I ' .. 9 - . . t .'.- , : 1 , --, , , .7 ! . , . ,.
Facility: .. '3r.i ExamDate: 1'F I
- Answer Exam Level '? Cognitive Level ?.F Section: i RO Group: SRO Group: 3 KA: iK s:, AK * .' RO VRO Value: SRO Value: '
System/Evolution Title F.i. I 1 t.,
¶
. t*- 1' p'..>
p.'I..v .i"'i.r. j F KA Statement: K,iow, -ip' i,'ir' r 1I( :Ib' .Cso, itrs.n l.IJ),1t s F3(oneit B,1 F rLF' IP Irteri'I A(nlmCt rustmctiorliss Explanation of Iinwmsrlt1-1C ii II) Iiurn IF 1t .' . .,iii . ,P '-2 'i orl B 0¶i.I'i N nt11l No Answers: /Oll b, Facility Reference Number Reference Section Page No. Revision L.O. Number Reference Title
'.1 '. .'t F ,. tl~jnt'l tiq 11 i X(
i S1 Material Required for Examination Question Modification Method: Used During Training Program Question Source: r.. .,v Question Source Comments Reviews Complete Comment Type Comment Peer Supervisory Facility NRC 1'
Question Topic , . . .- !
- T . , 4 . .... ..
.... 1....
t).
- c. .
e __ :.... I}I . I I Fwamr'iatr; O'-7 11/4( I,!
Answer i Exam Level Ii Cognitive Level . Iacility:
F..* n.
SRO Value: 1l Section: I RO Group: . SRO Group:
KA: C'II.r
- RO Value:
i7 System/Evolution Title ...
....... rL ...
.KA Statement: Kno,-ole>!,;- tT~ tt<tf< ~ t) '1'/t " ) " S lSsi[ . t t'l~ (.1-'if't.1ow O 1T~t IoiA I '.1 > i' ;": .i itlIt f t'lt lilt, r ' t (i)
(til '.hii 0 tly thl X 3/4.ttIi.'t ii q.Je .!Io 1) r 'r (.<r1/4 At he .bsrohed Explanation of A (orre ct St.ii 1ir-t[.. .tiII .i.t) ;i .o.! 3/4 3/4 rnto .iti Arttvyti i; iiifter .v%,IIfl?-imtiFert; of tie S( ;'OR~s
,;Answers: by the roid . 1I, -il ( t)kit Ittij tit Facility Reference Number Reference Section Page No. Revision L.O. Number Reference Title
.t m.i. r st ,-,irr . l P ,r:, ..
'Horr(! N;), .- S..si[Ir~;.tl Material Required for Examination Question Modification Method: et: ritt Sot.r: Used During Training Program Question Source: F iti iit F .t'i R lBll Question Source Comments .' b-! NIR Ov Reviews Complete Comment Type Comment Peer SuperviSory Facility NRC
Question Topic . , :, .; - -
A ( ,' 1 . ; r ;- . I . . I . .I . .. I : . , .! , . . . ., . . I -. .,.... i , I- I, , II . I ,. I I ,: ' - , - ; - -- , , - , ',
tr ! - i , - TI , - , , : , f I . . ,. I I 1, I . .1. . .: I I , I ., .! . .-, I I II . . . . . . . . . I - , !! i - , , , , ! - , ! , iI
. : . . , I.
,I.., I, . ! ! ... .I . I. . I . I . : . I .. I ! ,, , , , ; I ,, . : ., I -; - ! -. r . I '-, .
. . . I ; " ! , . ,T ;, -
. , ; . II . . , .. .,. ! ,
- a. I , 1.: . .. . .* I . .. ,' I , . .. .. .. . . . , .. '.
1), : i 4" .'. . : . I.: .. . ~ . . .: . I . I . .. I .I , ... . I.
- c. f - .. + .. I , .. , : ;. , I I. ,.-
d . 1 ,,i- i :,- : -. . , ; ." , , ! .' .. , - t ; ! ! ,'. t, - j: .. I' Answer i Exam Level :i Cognitive Level ( 1p -. I Facility: fir i ExamDate: , I r (:,2 KA: ( >' ...iA,1-. FA I 1 I RO Value: 5n SRO Value: 4t Section: f p'? RO Group: . SRO Group:
I.,
System/Evolution Title ,ti , , ,,::,
T (.lj KA Statement: At>i ,, lo ' .. , ,, ru,,rit , r Ift, f .1,, 1,i . *t . q I . o Steiun (T ' ir~r~t.' f R.t,,e:?
Explanation of (A)t (Cor,' t .. ror.*'. -lt-., e. ,1:,, ii n ~; n-ii~ t t. fell' p'nini,n *i~in, 'ri~dit urw' ire re,.i ht-(! ri 'nt~n I., lirve SG overfillI Bt Answers: Irv orre, I .fI,'n~ I~.n1 t'. prFi.._'i.i inn ,, :~e Jorw, ~ini! inrly re~j ni iej,, i-.id i t~iift tife ',I puinip whnich is -15fO N -o in i i itt)ij v() ,e~n t-i w i t ~!pvidwitiIi inn !?; tI.v J~)y rn! t ~; ;ilirips hni~,e rec i: lilies opin toi Wt.
Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number
, )(it,.c1k ;re)w, !' .;( i. t i-i.- 1;:. i' Material Required for Examination Question Source: Fa, Illy F ', l Re Question Modification Method: ::f1-it l t`,i-life: r Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC ZI
RO SkvScraper SRO Skysciaper RO SvstenmlEvolution List SRO SvstemEvolution List Outline Chancles Question Topic
- b. 1 C.
d.
Answer h Exam Level , Cognitive Level ApjiI Facility: ih.i :. ' ExamDate: 7 ln 1)t RO Value:
- SRO Value: Section: I : RO Group: . SRO Group: 2 I KA: dli)0 0,A2 11 System/Evolution Title S , I 'r *r , ' ',
o(
KA Statement: t , , 'i oFjIity n ri , t thi f l;I:,evi t ;-rrtr ,i;.tt,- l vt t ,I t i;itri',r TId. t,,
%1 Lo( t' rid ,, iehrr j >t1;I rniiiir tin I..1 Explanation of TS t f S . I *ie 1 i. t'(! ;jnt tn;I i'n~ SS( ( iii hr inn inn, n.,r t)niz inil ,., I: yirld iii 111.', t 1 A i .i yin <not it ii p' -,t i ii o(.1iiH t -i the nirnnimum Answers: intni, I.j I 'it <F i' liii ;
Reference Title Facility Reference Number Reference Section Page No. Revision LO. Number F i n; . ;I .1 .1 Steamt 1i
( . I *'. .1;-' '. 1 ',
! I, ;t, 4 11' [( I) .3.1 1 3 1 i A~o=!
Tech, S;;>,( , t ) , t))rt Material Required for Examination 1 ) Qetov( L Mo,difiao ,rf M( t hod : ; i- 2, alio 1, Question Source: I.. Question Modification Method: ! Used During Training Program Question Source Comments Comment 'Reviews Complete Comment Type Peer Supervisory Facility NRC
1+/-eskion 1opicpI I : ' "
-'. I - !
- r " ; 1 . .. I .. . I I : ; , -; . I . . , ,;;I I '; ; .! . : *I I1 . :~ . . I P I - . , . . .
,! .1 t. ., - , . .
- . I
- ~~~ ,;: I I
- a.
- 9'. ;I
- c. I; .[ ;) , f ,, , ' ,,,, , (,, ,,, it - , 1 ',
- d. 1E 1 -- A> : 1 ,, ,'re, i), t ,d1 . {,! .
Answer . Exam Level R Cognitive Level A.: 1 I Facility: f3ri 1.-:! ExamDate 7 190Ž.
KA: 0(;(), 11(; 1()1 2 .1 ,: RO Value: .1 SRO Value: l Section: ;9 RO Group: 1! SRO Group:
System/Evolution Title Sti ir, FO:ri. I ()4 KA Statement:
At )I IItt I; . ( ;r I. .1t b I I I II,1I !P ., ta '. n ( [ptt r -r,, .-d ii , a), n!. j 1 . I1 irt *.!.;
I)r a ! 'I :i) . for erner(;qer cly ainl(1
, )r ) r . I ,,qt. r . 9 I , : : , , .! .r I .-.
Explanation of P'r i F: ;: :r,, ' . ( I, -)rp, 1 ,' , , C I' , It 1) , I i i r Al II, ,,irhI r, 0 ther, Is A nswers: 1. rI: . I I . :I .,: , .. I r I.1 rl. I Il r II : . ,I I. I rl A .[) Irr rre(t Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Reru !,, Tf p ,, filly I- , .',' ,' 3 1 01N)V ( 1 Material Required for Examination Question Source: rN:... Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Qluestion Topic C..
Answer Exam Level h Cognitive Level Facility: ExamDate:
KA: (r'u};t)r:.: RO Value: ISRO Value: AI Section: FF' RO Group: .'SRO Group: .
System/Evolution ' Title : . 'r r'.* 'r KA Statement: ility t( ,' ,' ' i.!. , ' . 1. ..
Explanation of IA Crteve L I Fir .Fl It Cogi) '1r v:)r Llniririts Irly fI AkFac.' ili irri F(,S
- (rcdr qreitri Si f'oExarajae: and .
Answers: en';ue, tIFt. it frFt Rfau t r tow t: ti,irr'.irir:
Shu is al!u.,ruF
-kSetii to protnit t:r.Fir. FI
- iin: feI s the the Reference Title Facility Reference Number Reference Section Page No. Revision 1.. Number Fijrji::tiorri1 F(trt~ ' r,~F rF)A, I7,. 3 Material Required for Examination Question Source: Fri I.1rl *ir f .'I- Question Modification Method: IA
.i ii. Irt . Used During Training Program Question Source Comments l 'irutF?
Comment Type Comment Reviews Complete Peer Supervisory Facility NRC 0
RO SkvScraoer SRO Skvsciaer I RO Systeir,'Evolution List SRO SvstemiEvolution List I Outline Chanqes I Question Topic , . , ... , .. ;
Fr . . I.. . r.
- b. . II ! I':
C. , 1.' :, I1I,
' r IV, F k d '.1jl . I I.'
Answer t: Exam Level S . Cognitive Level Ap:I Facility: Br,,i , ExamDate: 7,19 02, KA: System/Evoluton Title [S, i B FRO Value: SRO Value: I 7 Section: i Pl RO Group: 1 SRO Group: 1 Systerm/Evolution Title S 1.sikoutl B1ll 055 KA Statement: rAt; In to- -1*to-rnrl) b.IUirditerp~ret t0), Mll:,-I:v :;, ¢fj:
9" ,; 1, 1t: S flkll< I(),1 o t Afcti.r- ,."d .ry *o rest:)rn po(r)F Explanation of rB ( ,)rro t p. r .'B.v( A t . "I, .,rft r,. t, ::.ir.1 -1*s i. B .I1I frr 'Ji, I rI 1 . .t, tl') . t tfo '1ntor rirerF AF Answers: rp i.,.1: IIt, .
Ar) rrw I(
I i ' ' .. , . I I .t I T 1'.4 t .'1i t 5.' 1 .u I JrI . I .q-,, r ,.&[)
n3
- .I '. :, :. . I¢. ; ;: , " ' :, ...............
1: -.. I.....I......I ...... ... 1 , : I 1 ... ;:1 Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Rr<w~or,,,e N,,()pp;o .it, ( Jrit t ,, .. )f A ] A( . 2f~i,,(,A It i .+plI NOT L 41 1 I Io Material Required for Examination Question Source: N:. r Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete j , 1 It , 1,(j trr, Ir I . . . ., Peer Supervisory Facility NRC i5
Question Topic . ,,..,
- a. . ,.o, ,:
C).
Jr !I . ExamDat e: 7I1i '12
--- - A I -. V - %I., TI . I Facilitv:
Answer Exam Level i uoyiiuvu - . .. - -- I
01)i , ,. i'",,A."I 4-. RO Value: ; SRO Value:
KA:
System/Evolution Title ,t.t ii B .,,
,t tht-,' i;tly f() SAtiwtil i'.11 ii .i, izotlt KA Statement: At).Iity t, (le terwj nEe ;irid. wltlvrprt tili f .1-1 ,i i .
rr.rjriilr t, .i* rsi' . r>.r:.IS .: btI iijr, riq f. ltlipq)i' .J(A B S- ,f,(
.,I ii [SF 'IVWItA:I(;('if control DC powe' r .n;. (. . 8 for t:' Io'-
h E' d . ii r i lir Explanation of I',i' l.t ;
A b .D In ruv ; i.Fre( rir((-,AI - 1(.(t)85 is a mrotor riiisn A .ill r .;'.I ..otII Answers: sytrenis ?,S.vs, wil l ,o Reference Section Page No. Revision L.O. Number Reference Title Facility Reference Number
.n'i Ii2 5 I t
.t , AI LE).% >
LOS. B .' N1I11t-. :p::.
6~.-t Bi-; Notr s-, t2'f .()( <,, :..
Material Required for Examination Used During Training Program
-Question Source: N. . Question Modification Method:
Question Source Comments Reviews Complete Comment Type Comment Peer Supervisory Facility NRC
RD SrvScr itr SRO SktvscraeIer I RO SvstemlEvolution List I SRO SvslemlEvolution List I Outline Chanues I 1I Question Topic I . II ¢. :
T1 . ... . I. . . . I.. . .
I...* .. .. *. :*
U).
a b.
C. .
d.
Answer . Exam Level Cognitive Level k.-i r., i Facility: ¢. o I. ExamDate: 7 1902!
KA: ()006)'(;,t ( .1 RO Value: SRO Value: l 6 Section: ¢ ¢P¢ RO Group: 1i SRO Group: '
System/Evolution Title St;ition Ol. (55 KA Statement:
KnoloesI(!e r of O . .j I n )Ferl .it. ' ' t, I. ,t1 i II tItw )T 1b I1( 1 : i .;ir eU i IExplanation of FPej EP AAk 111 rNtifi(,itIIIIo.. )ftfIie ale(utof
( - s t)b r WI AltWitthl' 1 In fI.
u1tIl.'¢, ll', .ifi,it) Itf-lt'I chtTq.i (Ai is Only Answers: corre t IliTIC frlirie Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number N tf ¢ -. AA I.:
- 1. .1 1 1 Material Required for Examination Question Source: N' : Question Modification Method: I Used During Training Program Question Source Comments Comment Type Comment Reviews Complete
- SR() A ¢ l t )t ' )o, tl - , Peer Supervisory Facility NRC
OQues~sorn 'Iop)ii t)
KASt t me' ' t ~
Io, n',) I-,w11t-., ~ t ' ' v ' '
A,,,io, . w. rI . '. '. .'.r o .l' .r Answer Exam Level B Cognitive Level ',¶trrry Facility: kr :.. :ExamDate: 7:19 KA: 'fL`I1K I ' . ' ROValue: i SROValue: .t Section. RO Group: SRO Group:
System/Evolution Title <. P .. 0!58 Sytmrvlto Explanation of I Tled
( e'rres wd I Ire . itrtr[i the 'r I, iti VwFS'
';.*rwraltw -1I iw.'.C1 1 'r ' rrI to 1 1 ii ii (JAI;'
i,t .K" rs 1.1 ji ii I 0y~
- . 1.7 %ill 'ive lst breaker c)rol power Answers: ird rire AB T.. Tti, .lo.ii Ir:i r irw 1"i/ .1 itterdterit I 1>4. turn thf. V .4 F ririt. r is Irni~as t' PMG rern. lins Anslwerl E'xamrLeivel.B i I Cgiv Litrniti, ',0 (1:50(1 aid iri rot J.l DC 11 D r .rr lixnmvaate,:
-ittcedwatr i.:o. 71il Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Al. . ( )p. ilw Pro Ir- j 1.:;.; [ . ; ( 1 Atti: tit, . 1tA; S 1'!(1 B.':t B.(; N*t.
B..( )A EF M ( l . ...n PtIr II ( );' I i ( .1 .
Material Required for Examination Question Source: F . It irr Ii. Question Modification Method: ( ,.,it 2.1 . Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question I optlC :
- 1.I' 'I ' ' I !
I F.,i f I 11: :
a1. I I
- b. I . F I
C. I < :: , I
- d. . . .
r.', ,,, , Facility: h'.1 ::.:,od ExamDate: i, '>12 Answer Exam Level i. Cognitive Level C>^I OU onrl,r ......
RO Value: .; SRO Value: i Section: u ut KVroup: . . ffr r -
KA: 'I' ,,fr .' AK..a'I' 06(,
System/Evolution Title A. ! I. ( .1111>' R .; I .*. - .r .-
1 :t.- :<^,.1(..., ,.. ^ ,:,!R(i, ; 1(i,,;,
KA Statement: KZ,>e!;o ]WItrrlr !,, ;.+..'.
A rj,' 1 d'f T1; ., l.Tlr to i ot.r iT.1) Ati' - ib- feI ( :Ii , Il f3,rc..?I f III
. tj) o()r TuIT o' tIle clhlrc(oai ,ibsorber Explanation of Ho ri: ilvt ioi* 1rorr (JfRTARt( 1,.
rT i::.-.
- T In: of ther Tlr ;:itI3/4) t~[KI'. ( fiITT Ir ;i) IS tit, onily mortAe t aI swer A nswers: I leit md omvill m(rll:rrs mmli <illt. I ml)Ltr Facility Reference Number Reference Section Page No. Revision L.O. Number Reference Title Ar mw L ,it
- R iI-: Ii 1 I t 11 *:R 1 W l AR :'fi t '
Material Required for Examination Question Modification Method: I Used During Training Program Question Source: Nmwv Question Source Comments Reviews Complete Comment Type Comment Peer Supervisory Facility NRC
Question Topic ' .. ,I I
.' I , ; ! - . . , " .. . . . . 1. 1, ; . . I , , !
- a. ..
t) ;.I .- '
1),
C.
- d. R. ,, . f Answer (1 Exam Level f Cognitive Level A; .nit Facility: K., :..., ExamDate: I 1. 2 KA: <it11 :(fi.U.' aw t RO Value: A 4 SRO Value: i Section: pm RO Group: 2. SRO Group: 2 System/Evolution Title a. 'dtr!.gI I .I t . x"..,v, p .j. (,ti(
KA Statement: Kno,%de'::-A s Pit t1,, . t,. is t, rAi., VIt P'..
A( '. t.R.* J.i.'.pr:
i1';.l ... 5 r ..At iIsrl Explanation of f',r TS bi. ... 7 123:I (artr I t, q :,.i 'yis I'strliu,.Iati,1 tr( ro .L )( A Assimvt.. I parsasve ECCS tallure olitside Answers: (:cofitainiltrt 't ,Ih . - .SI ptult I ,. t vd 2 wtt Io ir t iurinqi(o lfJ r.t, in,: (A ( . irs :11( Irr
- I it de(t (:ortflarrrltert tr)(:(otjrirnq Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number I TS B.r . . 1.' Bi. 3 1 Material Required for Examination Question Source: Ne.-, Question Modification Method: I Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
0uestionrl 1(TpIc . - , . . ., I ,. . .. .. . I
... I . . .-
- a. ' ; ; , ;*, I CX. '*' . I :..:
C. I I . . .. II
- d. ' , , - - ; ;, , 1 I, , ,.'
Answer I Exam L,evel , Cognitive Level r.l Facility: ;ir ,,,! ExamDate: 71 K:
2 KA: ' nS(1. 2 ROValue: 2 SRO Value:
Section: i i1 FRO Group: 2 SRO Group: 21 System/Evolution Title 1 A. i R1Irr it It r . . 1 S ,Ar ,
(Jn,1 KA Statement:
Explanation of A ,,::v;(J ir oI rl
- 3i ,;)[t, fir , Aliirt L ofn rni pi fA ,1 ';,r I, oily rNut tronn iiIi ! A (. j ire (orr,(nimt fturct(rrs ot the Answers: trnrri' irfed radir fitrr Irll torin in; ,y,.tmnrn ID) T'ic vi ini(,crre S ( urrn' nmi t .tr Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number No rfl` 1I t In; ' r, ', IfI B.-A '.,A
.'1()
R idi ~iti,~ (- I. I l' #'......*A;4 x...l$' I; Material Required for Examination Question Source: Nr.*, Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic . ,
i . i I . . ... .... ...
- s X . i e ;
- : . i : p. - , +
h , .2 I .
d( . I .. , i (r ,e r !
Answer t Exam Level fi Cognitive Level Ap;.i it Facility: iri d.% ExamDate:
KA: uii:u,)AI 111 AA RO Value: i I SRO Value: . Section: f PI RO Group: 1 SRO Grou; System/Evolution Title iw ,, ., . ,. r., V.,.' CIi I KA Statement: Ati-t, o , r,l9 , P1 '1 ti .'c.1:; t.
i' of % 1'.-r'.r I.
I Explanation of 4A, r orr9(c i(.Ic. tit 1 tn.t I'.iri~,*r p.i<h w tivi irvcKr ' . .( 1) A .i >(orre I per 1E.:.()A PRI 8i ,itti, is B stp it)
Answers: RNO 1( i r( or-r.I c:t ((;.It i 1r t *irIoit'rit lrr.,
ri(p pno'rt. prr?
Ir -rer f :trm, R(.f (s 9ncipabir I Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Nlumber Ath i or-,fl r P-, ' ,, 'ljelf.(, ;"?1l . A". ht ; -, I->X Material Required for Examination Question Source: Fi I , F 9,11 fi i Question Modification Method: S. rr!fi,'. 1 : Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic
- I , : ". - - .
II 1. . . 1 . .1 4 I'll . I I. . . . . , . I
. ., .1 I II aa.
Answer .1 Exam Level ' Cognitive Level AtI ith Facility: hIi' ExamDate: ' V)(2 K A40: :4 , 4V RO Value: 41I SRO Value: '.I!Section: PE RO Group: .i SRO Group:
System/Evolution Title . tr~rin (Lb" KA Statement:
A ~t*II 444 ;.. t .rI ,
- tI.4441 ~,
r , 'r t , r ,~1,j ' i, I i I I , . . , I'll4 4 *. i% t 44' I ,.1 44 4 I )4IT~ ,;) ~'I .4444I, Explanation of IL o'.' of D( Bi,, I111 hi', o4.4149r444 .'I. 4v141444I'd by ~Iltiiini.Ifit4' 1 21 ji. 'i i [D( h,j' voIl iiqc Ir'4fc,ito ~rL w',s oft ESF D (' res4Jlts Answers: in',,, of 1A tr, 71h,m44,4 fir'l re';il.i~iroil iI,;(-s O O?r il0 l w ed'44 ;uwr w~'iII4. I NW1RVs re';i.Ils. In or re 1wjred allr IrulrmlriIle I -n..., .. . . I. . ... ..r . ... ~ A..
. . . .. vt lc
... ... L .. 'r ' . : ri I . 4, ..i i . . .
... '.. 1 ~i i i ~ ri I . ~ i ~t l ' B I ' 1r ( c - 44 I f (I I i,Tr iinA 4, t*.t.i, 4 11 b o p e ,] i- :;t. Iy t p '.'II
'ior' it'il, hin il err Ii e t I4I r , I 144* [)f(~ t3 4. 4I r G rrdl .144-.
k4.'d 1(i io l 0- ,4 44l1
.49t w4 t 4 4It 4 44. 4 hI 4 1) , r - Ii ) . ( (1 ,f .J ) i . D B , l s w Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number A b nt1(,r4i4,4I ) 4r1 l r Pr :, L i. )( E~ 1 )L. [~LI ( r -' .44 4 I 00)4 Material Required for Examination Question Source: N I -' Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete I ). 4 . 4 * , -** 4,, . fl I , ; : ' '
- , I , , -, * '. , . . . 4 . 4. , , i. I , - '4 -~ .4-Peer Supervisory Facility NRC
Question Topic .. ;
. . I . I . . .) : ' - 1: .
! ,. . .a.
"a , ,. .
C. -1 ! m. ' I ' C I I -.(] I Answer .i Exam Level ¢ Cognitive Level I.' I -mm., Facility: Hr[it , ! . xamuate: / i in.
AK1 U RO Value: . SRO Value: Section: PE RO Group: SRO Group: 1 KA: l(Ji im.m' 'C1 System/Evolution Title .. mti w limt- ,.;,
mit ' i 1:1 mA. :m 'I'm ' I'm. in amsmot ( m mm' of*CI-, ommt 1. ort' nrm.imm KA Statement: Krm...i ..;. I,ttr, m^mt T' ) in i t ", t , r.'.,,,, mm . , rm.m Explanation of nt' -1 (X A r mj,'f'mliI Ifi' r .'m '. :. m.mmmiy r...s' . ir '.in' ..:mrmt .:.?'
- mino i'i'mm Il rerirbl Immimlvf'rtcimn (CS aictjahtiomr wouid(1 Answers: .uin.i p - .,,rjrf to ' it11lR( I' ..P ti .in .i D [)B I ( )( A '. ltim er rmm',. airnd n.'rgy reler .
Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number 11F RXI , ' 11 2 * .
lfr r~
R
- 6 .1
- mm Tec'mr .i 'I; -- i ! in.1 Material Required for Examination F.i, Il tv f -.1m' RAO't Question Modification Method: I D'r (t Frmmmmm Smk.r . Used During Training Program Question Source:
Question Source Comments 2mm -; B.' .* rJ m Comment Reviews Complete Comment Type Peer Supervisory Facility NRC
Question lopic :. . . .-. *.
,.. I, .
a.
h C.
d.
Answer Exam Level Bi Cognitive Level A: I it Facility: iv, . -. o1 ExamDate: I !ti2 KA: WI.
- 1 K1 RO Value: 8 SRO Value: i1 Section: I P1 RO Group:I 1' SRO Group: 1 System/Evolution Title Wid-il' .it. (,t,- Ihi'.:
Explanation of riI:iIki~er va,.i~t u,.tt thi i tr A'-i prf f*is oft -Iri') . i- ~ i~f - it
, Ti-. A)-167 f-5u F siit 00Cl-d is .117 F Ps~it for
-Answers: .11 s 3O-) p-. -I - 2hi5 tpslt Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number Steatu T i Material Required for Examination t'i I:I-Question Source: Fv-i'lity E x~it'i B3,iit Question Modification Method: Cld oriilly Mu-I ft-led Used During Training Program Question Source Comments t., frt '-wi It -tI--,, .t ,t--rt
.- it',i'i)
I it *tu p ,, viA hit F I- . 2iP -. A, Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
RO SkvScraper SRO Skvscraper RO SvstemlEvolution List SRO SvstemEvolution Ltst Outline Chances-l -_i Question Topic ,
9'.
',b *l. 1,, : , .. ., ;, .
b ; *, ' ' ' '
- d. 1FR* '.:Y,:i o, .
.,,,, 1,, -.1-.
Apnplu.., Facility: Br 1\' ExamDate: 7.19 02 Answer b Exam Level 13 Cognitive Level I EK2 ()'3 RO Value: .' SRO Value: .W Section: FPE RO Group: 1, SRO Group: ij KA: 00007tK2: '
074 SystemlEvolution Title 1, vl!eqi I. ( ore ( o' r; Kio.v'11;ltolof'th y'i, 1(.'... rI lpl. (11'yl ((:01' 1 t le flollI471::
.11<h KA Statement: wt,1rr([.lI I . .. - 1. . I [ 11 I~I
- 117717)17 1, 7 ii rlvxil 17l)1ef 1he 110nroll4' from 12H' t 117J1
- l'(I 7 ttll' r((-o t t 're iiJu 11 1 it ss on he 7
! Explanation of B (.0orr( I Dec.1l i 7 r'er':f' rlo
'1.,7,c: qle1 7 ) th f,117 ip ond rir(t r1,mily ,lIIJ 7 1(0) ..ope1 A Irlcorre, t d11crle,lilliq 7(!17',id m) 1(.V- 1M2 will r(( t (t ((re.ase 7:hd1(rgin1g Answers:
.i ,plray v.' iIvetv.,iI '? t 7 qr( 1:ll. t1(.', ti) t11, ::r( tre7:Iiw.1. Were 4,110 n, 17), R(:P Rr t, 7 ,
r,1 tS Itt tto Rn 71 ,ilri Facility Reference Number Reference Section Page No. Revision L.O. Number Reference Title
.1 i
,. ; 1 RH 1 IB.vE)F r Ti;) RI P .'.Vd,-
Op A(T\17r Si 01177, r.,
Material Required for Examination N:qif-Question Modification Method: i Used During Training Program Question Source: N".:,
Question Source Comments Reviews Complete Comment Type Comment Peer Supervisory Facility NRC
Utlestion I o;)i(
C
- d. .
I" Facility: Frii' ExamDate:
Answer Exam Level b Cognitive Level KA .WKi~:.~ K RO Value:. .. SRO Value: i Section: s ~ RO Group: 1! SRO Group:
System/Evolution Title Rf :i )
,f I KA Statement: ,.i, !rlUn,
,ft, ,. .i-:;'~
Kro, '. I . . i i? I i ,,ti
. in en', I pN-,'i e1 ; n , ,. in levo'I voold decrea¶,e as Explanation of . A. n )rr-,t ,, . . ,i'i. r.
pr n- ,nr.. ,
in I T1i'ii
+rorin Leyve:l n' of run wnthdr.i.' inn t r:renr'e nls!tjre would decrease Answers: TEam.ve'e.i'e*I f.i ( ( reo I Facility Reference Number Reference Section Page No. Revision' L.O. Number Reference Title 1 2)
Ti. i1 RD :' -1; Roluti IF Material Required for Examination Question Modification Method: ' '1 I' fInlly Yif*Iii! Used During Training Program Question Source: ,i, I y ' x,,i, Bnk Question Source Comments Reviews Complete Comment Type Comment Peer Supervisory Facility NRC
C ::
- d. , . . .
Answer ! Exam Level i Cognitive Level ',1,rrwr, Facility: ivv:.e:. ExamDate: ln.:2 KA: (,01(OK61 1 ROValue: s SRO Value: ' Section: SY, RO Group: Iu SRO Group:
System/Evolution Title !rrI :t, r e 'I' ulu1 o.
KA Statement: KI1v):.Ir,1 1 (:Athe fAfI-t )t ZI). i 1, in'i. r11 e ' b IW;r i li. (hr (19 Iti, CIr)Uro Rk d t)rlod SDr' L .t r,, .,, , ,f'l(*
Explanation of tA vircorri I i:Iri. y fr dtill A f.i, rt l rierr tI A ;it t i i ifts f, :r '., kIre inn.llt (,it)hrrts or droplel)r I1 (
Answers: I I lCrrfec(.t - rr o 1. n.t o b t i D) - 5 aorrethlt. to f u(( rsr( ,%Qitti itc rvrr y orldrr LED irncrIcng fo(1rod poiti!n Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number '
Bv,1.d .D ,, t)+ 6;r,..)N Material Required for Examination Question Source: N. Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic - , .I . ;.,
- zf .. .. .' 6. : c 1, - '. , , !: . . I a ,,
t, : . *
- d. . , , . .. I t Facility: Br ii !&, (! ExamDate: 1(702 Answer Exam Level B Cognitive Level AHI; iFl I Section. SYS RO Group7 . SRO Group: 2, KA: l SK0 K IU0 K RO Value: . SRO Value:
SystemlEvolution Title tit ,r .i Sy ...... '
.r F ( Alt'l N 11 h.ii'v of r.l F t I .. 1 KA Statement: Kri.I f (, r th e j irfv,;', t, r i, .:r ri , I *r i.. IR 1 i r F,,i iti '1 ( iistil Ii . t1. i ri ii,rD A B 3) t rr(r ii , rrt ,. i ci s-sriirr itlrr eFhc irr1.11 Explanation of ( (<)r r >o - orilry R(;S r 1 i ;,,.'il
' (li Answers: direction rrdle' o' Fli t Fr or . ()(.A I Facility Reference Number Reference Section Page No. Revision LO. Number Reference Title I1:F' F x 1f1 IDiFrirt Intrco to l, P Material Required for Examination Question Modification Method: Fdlit ,r .111YMrlo(ifre Used During Training Program Question Source: F-iv I ty E -iri B iri Question Source Comments Reviews Complete Comment Type Comment Peer Supervisory Facility NRC
RO SkvScraver SRO Skvscraver RO SvstemEvolution List SRO Svstem/Evolulion List Outline Chanaes Question Topic a
b.
C.
d.
Answer Exam Level s Cognitive Level .1/1 y Facility: B ... : 1 ExamDate: 7 'I4 KA: ( 'eA2 Ki, RO Value: : 1 SRO Value: Section: : RO Group: 2 SRO Group: 2 System/Evolution Title Rr i 7 lu O()2 00 KA Statement: ;i ' 7,'n IKt7.v7.
- t ' .71r djr 7I- l'7117' 1,11 .1.0 . .I 'ii.-', thtI,,, t:ir ( 77' .Ii t I'7t Re~i t: r (i .'
r3.'df r1 Explanation of tr'y1 t,, 0i S '. '- iiia l , ,'Ih .' I, l,,I h10t ir.
,,,, , , 7 .' ,,ict: ,,1', 3 Ii.'
I vwr7-(7 i r, 1, 3i r77 a -:i r ves'-l ;
Answers: . pr7i7 3 ,f'I 'i . it r 7I't i7i ;'fly r , <7ior '!
Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number IL T B,( N , tU)R[E R I5 1I Material Required for Examination Question Source: N.'.N Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC qo
ClUeStion Topic i
- a.
b C... .
d Answer ! Exam Level B Cognitive Level / I Facility: fIr -... ! ExamDate: I ,' 1.2 KA: ,(, i: -,A."()' RO Value: .' SRO Value: I 8 Section: ' I- RO Group: 1l SRO Group: 1i System/Evolution Title tir ( I.I f' :. S . (FY)
KA Statement: rAN Ity to f I')r ! tI FT' ,.t.* 1 t'If .s ' . I'... , ,,If ( It f'Pt(1 it -. 1 i t i.i<*f ' 1Fu w t- p)re(dltItr- HJ¶('
p)f,w ( <S!jreI ):,rr, I rIt .: r IIl~
I II t I II -. ;I, I r 'I I .. .1I oIFI,r1+: I 1; I rI I I E~tII (t f '.II(.T, rlt, .r :rI rq ;' 1l I. S .+ 1 I Explanation of (C) corie( t -rc:re.,;irF Ie. u rI If t r' rb 1 r o II. ItIIi r t r r l t).i.Iik ',(3/4 rIe 01 Iti I R(.P s, (i e r.1 (; # seI Ie..ot Answers: flo.v Ver'tqlr"1f- rl'l'l . 1 tt I VI( T U t. -(e(Ir, .uii I ! air tIvfl. I() N j(deq-i.SII;iru TI (R W S A"RI .ANR -ororo:t b.I( k)r`essLjre corn(ri)(on,,it for r {! VsS
( T 1r-'rS r, . .Uu( S. i
- vI II, viif. wiljurrn to rrnirirl plrfi. ,rs Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number fIA.FI 'I 1 I.5 '). , ; I(- on;
, I. ' . ', F ,¢ ¢,, ,I 1.: ji Material Required for Examination Question Source: Nf ,. Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC "I
Question Topic - ,K,;
- ) I :,I ~ I , -: , . , I I . 11 ;: 1 . I. . . .1 I.
a.
- c. rrI..
- d. ( . .
Answer t, Exam Level k Cognitive Level M!.' rT rr Facility: ir i ,* ExamDate: / 10(),2 KA: 'i(r: 'K4 1 K 'l RO Value: . SRO Value: 1 Section: RO Group: 1 SRO Group: 1 System/Evolution Title R, I, it t 1'. Kr ((3 1
KA Statement: Kri ,' FRe.v 'or (Co .lIkr' (Jtr :' '
rr ,.t 'rT.:' i feitijrf n or r k d. r lnrr ,lorIrr torIl..rr
.r;
/(rtenqn .i*i> ..*r In~ri~ I Fi~q .: in r ir r! ii Explanation of (Bi (Conrrrr t Ir lintm we rt r ir:ool' crln, t)(- X1 ¢,r1,i ri I Answers:
Reference Title Facility Reference Number Reference Section Page No. Rev vision LO. Numberi R(:P Lpy,ornr Ph1ir 1 F( t, r '111(1 34 I . .1 I I Material Required for Examination Question Source: N, . Question Modification Method: Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic I . . ,lI .
I. , . .. ~ . I .. . I ..
't i t . ,. . ,i( , -. .. .
- , - I. . I~ -.. ' . .. .... .
- . , I , , . ! ;
- . . . ..
h v. . 9 . : . . . . 9 -
C... :' I. ' .,' .: .
I:'.: 9 I. , 9' ,,-' ., -14:;
Answer a Exam Level ( Cognitive Level A: v Facility: bri. .:. ExamDate: 7 1'I . 2 KA: (00.4(l (iA 1i Al '? RO Value: t. SRO Value: *. Section: S f RO Group: SRO Group: l System/Evolution Title (.'1 - (;l ilid %!,lIhlw ( ' 11) ',).lr1w (,1' KA Statement: Atilily to :.rf9fi Itiwlo . ) 99on,!r in (o
9(; 9rfit.4' orpertitr,,ii (J.-199 r.,i . ! '. I:Ak.9' (Co'lfr* SyIefr9I
( ')rub, .9, 1u9!r9 R(.S pr( . 99 ,)i9r9 ! 19rs f, lijo9 Explanation of Ai (Jorre ' .,it 119,.99 I9 9I 999iI. . ful :! o I. 1 99 i i t'99 v ii.ilt 01n9 v9 OyI'ov.rr : r99t .v,Il
/!eVs) rsult :
!Answers: irt lwir; valiratio, 9n p,9-9..9999 Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number
(.V( S ' 11(,'I X[
I; 1 R(.S F I ,1) .'99l Vi E..U'f:' i ? 1in 1 Material Required for Examination Question Source: F. Ii, [y F Xw9 R999 Question Modification Method: [)Di9( t I r:wr i ' ,. Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic . u
.'. ,I : . ,I I ;
I . . . ..
- ' r a1 I . 1l S. ;'
.... , I ....
.; i . ! .
- d. . *;..
d.
Hi II! ExamDate: 7.1(i H; Exam Level P Cognitive Level :II r tI p .I Facility:
Answer 1
. Section: S ROGroup: 1 SROGroup:
0)O.V(il'. -W .. ROValue: . SRO Value:
KA:
System/Evolution Title (U .i .Hi .il.' ( iie 1 't' KA Statement: Kr io I~ i- r ti , .
I hi ( I. r .1. ;ppl . r t+ ;.ls.l.
f.l( )V'
, :Ner,( t*:
i(.;A
'VoJ B3rir ie I -i thtwe aireb E SF powered ID (:rrr I: 1te ir:ily '1 '*1est-f po.-td MOV iri tlil iii 1( (
,Explanation of val;, s nd .vvil be et riri.d(; 1t.i '.' n ir lo s of Wf ,ite by 1I'e rrf.:eive ED(;s I Answers:
Reference Section Page No. Revision L.O. Number Reference Title Facility Reference Number B.H()F' (:V , 5 CV EIe{: riiAi Lirii:
Material Required for Examination Question Modification Method: Used During Training Program Question Source: N :.'.
Question Source Comments Reviews Complete Comment Type Comment Peer Supervisory Facility NRC
1RO SIvYcraptl SRO Sk~.scrai~ef RO Svstem(Evolution List SRO SvsermlEvolution List Outline Changes Question Topic C.2 An~er2 xamLeel: ognIrIVe Level 2Ok ,w Facility: B.~ .. IExarnDate 7 1)2 KA:; 005000K30)1 K3 0 t RO Value: 3o SRO Value: 41 0 Section: Y-S RO Group.: SRO Group:, 3 System/Evolution Title F'woi:o!IA He~ft fPerov.il5,'i KA Staternent: KrtowleIdqe-of tthe0 f it(I'IIIAAht's 22'i ,jmtonl~ otf tOh' Re-,i(12 ,iI Hvi! RerjjoVil Sy~t.'ni .~.II 0 i~.eonOtt hto iowing 2
Explanation of (A Incorrectilsr fte(¶CI2. ~I n tr;~isttnr~r )I'ot~ C stt52( orc e Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number t 26 Placvi~j',tg e RH syste't in S D Coil it; ,B.'.: RH 6r' 12 Material Required for Examination QuesionSouce: Fei~it'y F ;ir)t B~irk QetoMoicaon ethod: Ed'tor~iily Moti f ,tId Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic a
b.
i ' -. .
CCi ~ ~.',..
)' ' ' !'
h N, . , -.
Answer t Exam Level Ii Cognitive Level ( ii: r' . i Facility: ;t :
.. ExamDate: 7 10o(:2 KA: 0('5WI3)'K5i r) K 5G/ RO Value: .' SRO Value: 1 Section: (, RO Group: 3j SRO Group: 3, System/Evolution Title Rsv~.. . . it Ri mn,..
KA Statement: KIr'u.le-;I ; of the 0[i.tI ibII i' Iu it ii'. 2 ti foiikiA*ti CoMelipt. as ttihcy .cei;y ',, t'.. ,lit Rell'oiil Systenii HR-..
Plant do.i)iisf.
diriri; s pl i it- po-,'i(ri.. l Crii (;(' d1ki to t9e riI.itivii inc O ri lSit of :Atcr
.Explanation of ,IBJ Correct Loss of R'H -o.ulrngs 11i i.l allow RCS to heat alp ICV 131 wIIse p'te.-tre droip as RH pormp is tripped and Cose Answers: *o m.we R( S pr'.i -,. -Ai ricoiro I pi-rn'I i~ I n(iree a &[
P o orre i R(.S . I. :it opr i.1'R ooiiiii is licst Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number
( -, - . ( )) . 'ii, r [', . ! .r 1(,() , U D 17 Material Required for Examination Question Source: N' .: Question Modification Method: i Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC c4,
Question Topic . : . . I . - I
~I. ,. . . .....
.; , : .- !-. I,-: P: .- : ;
.. , , , . . .. I . . : ; I I I
. . I : ' -" .'. ' I I J! .- !
a.1W) i. ': , ,.
C. " ..
- d. : . . F i!,. . , , , , , , ., T Answer i Exam Level 5 Cognitive Level y.'rrr':r, Facility: ; I
,i"..: ExamDate:
0
KA: liK()
Eri'- ;, ; (. - . ()(
System/Evolution Title .
Kno.vId~;i e : I r'ior 'I ,it Iff.
f.-in w !.r nt -r I iov:(Il-h,.1il t lhe toii.. nii KA Statement: ,' C(ore :ir';r S. iftty Irif 'I t ImI I Ilt,(
jj 'l !). i,'.
8281I (I8 t)NI[) or 1, '1; 1 .. t'..
Sl85 thf. . tB iiterlo I to open ite RH crosstie Explanation of IA) (corre! t :],;:,'q elpif-r I2S 2K A r'.t Answers: 2RH8801B (B.(. Di limorur t Ir r ii ar. iir 'e iterlork ( Ir: try Reference Title Facility Reference Number Reference Section Page No. Revision L.O. Number G(Ps Aini (o>ulr,,l Br' vii, rK, ,l . *.x 1 1Ai 2 Material Required for Examination Question Source: Ne.-, Question Modification Method: , Used During Training Program Question Source Comments Comment Type Comment Reviews Complete Peer Supervisory Facility NRC
Question Topic ire' ,'zr R- el 1 laii u(jerrc Tdrk Systemn lPRTS)
The NSO has IX ted in i(.reawsi; evel in tIe PresSojr ier Relief Tank (PRT)
V/hch one of the follonog RELIEr VALVES might be d scharging to the PRT?
- a. 1CV8118, Charging Pomp *t scharge relief valve
- b. ,CV8117. Letdown line orn'ie relief valve
- c. 1CC9426A-D. RCP fiermal barrier relief valves
- d. 1S18856A/B RH Pump discharge relief valves Answer Exam Level R _ Cognitive Level rMemory J Facility: BraidNood JExamoatej. [ 7/19/0 KAj l'0700l A301 J 01 , ROVaie: ?2i SOVaiue j Section: SYS Y ROGroup-i , SROGro4JP J__
- Systm/Evoution Ttleb [Pressurizer Relief Tank/Quench Tank System J 007
$aStatwmntGI Ability to monitor automatic operations of the Pressurizer Relief TanklOuench Tank System including:
[Components which discharge to the PRT 0pbn o °f (A) Incorrect - 1CV8118 relieves to the VCT (B) Correct - relieves to the PRT (C) Incorrect - relieves to the Cnmt Bldg Floor Drain A06w r.t .Sump (D) Incorrect - relieves to the HUTj 4
Rferocec Titb ;~ [1iPacUKitelieuhe RH--f--imne Section l IPgj NS dwwtbe L lP&D fV-6 S I I _
_- .- _ I - _ _ _ ----- -.-.. __ ___ ____
aterial Required fOr Examination J-
,Qt ionSource: Exam etnod EditonallyModfled_ ]Ud DringgTraining Program Question Source Comments 2001 Bwd NRC l Comment Typej Lomment 1 IRke v Compliet
_Supervisory
. : _ _ I I : ,. _L
_~ _ _ -- - - Facility NRC 4s
Question Topic Conwocent Coolint; .'Jatr S .stern (CC'v%'S A leak in which of II !oI , , ; cornpon tns , Ill restj I in a3natIlo q atic closu o/of. CC' 7. Component CoolIing Ski; e TeTnk Vent Iv e&
a., Seal Water Heat Excnanqer
- b. Spent Fuel Pool Hea. Exchanger
- c. Letdown Heat Exchanger
- d. Waste Gas Compressor Heat Exchanger jTsw Exam Level lR Cognitive Level Application j Facility: 1 Braidwood j Examr ate: ] _ 7/1910 J1 KA: 008000K03 K103 ROValue:l 28 'SROVaIua:l I 30' Section: !SYS _ r S tytemEvolutlonTit i Component Cooling Water System _ 008 sitatn-] Knowledge of the physical connections and/or cause-effect relationships between Component Cooling Water System and the following following _ __ ___ ___ ________ __ _ _ _ _ ____ _-______________
PRMS _ ________________________________
correct - RCS letdown is at a higher pressure than the CCW system and will result in inleakage to CCW. (AB.D) are all at a II lower operating pressure than CCW and will result in CC outleakage. (see 1BwOA PRI-6)
Reference Title - FacilityR Number Riferecetion 1[Page No3jR .V N w mb&
Big Notes CC-2 __'_Leakage
- - --- ach Sourcres r 4 rL FComponent Cooling Malfunction 1BwOA PRI-6 jAttach-B 730 100 Material Rquiired for Eaminat-ion ,
Sduion Souaret ' rFacility Exam Bank Question ModiTSon Metod Sgnificantly ModifiedljeedDuringTrainProgram l
-Flon Sourcet Comments Ty._ Comment _ ___
r- ---- --- - -. __----------------____ - -. P
- - r _._ __ _ __ _ =
Supervisory' IFJ 1 1, - - - - - - -1 -- -- -- - - I FFacility I NRC
Question Topic riediignos.s vith Unit 1 roperating at 10t) pc.%-e the follo .ing events occurred
- A reactor trip, coincident with a -ss of Inst irnent Bus 114
- All systems%responded as expeo ed after the trip V.' th NO ope'ator actions 5 mnt I'ter the trip Steam Generator water levels .ill be
- a. HIGHER than normnal post tIo response due to a delay in ISOLATING AFVW flow and the Rediaqr'osis procedure 1BwEP ES-0 0 should be used
- b. 'HIGHER than normal post t' - esponse eue to a delay in ISOLATING AFWJ flow and the Rediaqnosis prccedlure IBwEP ES-0 0 should NOT be used C. LOWER than normal post Inri response due tc DECREASED AFW flow and tfe Rediagnosis procedure tBNEP ES-0 0 should be used
- d. LOWER than normal post tri~ response due to DECREASED AFW flow and the Rediagnosis procedure tBwEP ES-0 0 should NOT be used lAnswer3 d ] Exam Level i B _ Cognitive Level 3 pGomprehensron J Faciity: iFBraidwood ExamDate: 3 7/9/0219 KA fWE01K202 OO , EK2.2 RO Value: _3 SROVakh.:I F381 Sc Ml E.E I ROGroup:l ,_ ,SROGroup 1 SystemifvolutibnTitb IRediagnosis I E01 KA saementil Knowledge of the interrelations between Rediagnosis and the following:
Facilitys heat removal systems, including pnmary coolant, emergency coolant, the decay heat removal systems, and relabons between the proper operation of these systems to the operation of the facility.
iExppndbn of A loss of inst bus 114 will cause the B train of AFW flow control valves to close after flow is sensed through them. This reduces the s __total AFW flow to the SGs, reducing post trip level response to just one train of AFW vice 2. Use of rediagnosis is limited to those I C.3C. IC -.0'3 -...I -. a.a - * -, . --- ... I..-.--- - . - . . . -
valves failed open not closed C incorrect - rediagnosis does not apply D Correct I Reference Title JI__FacilIty Referenc Number Reifren Section Page No. J R ILO. Numbr I Loss of Instrument Bus - J 1BwOA ELEC-2 Table D 18 1 ;A _
I! Rediagnosis -[1BwEPES-0.0 JPurpose -i - -- j
--- - - ZiC ____i rL -= -_ __j7 aIbrlbl Required for Examination Question SOurCe: Facility Exam Bank Question ModifIcation Method: Threct From Source Used During Training Program 1
_____ _ i ___ -I _ _J QuetonSource Comments 12001 Bwd NRC
- - .-. _. - . . l CommnritType] gomment - Lve R I I _--- =___=__=__ ___= =--------- - I -- ----
1,-- -----
_ 1 --- - - - - - - - I___ I I
Supervisory I
Facilty NRC
RO SkyScrapeir lSROSkyscraper RO SystemlEvolution List I SRO SystetrEvolution List Outline Changes Question Topic LOC A Outside Containnment The operating crew is responding to a LOCA outside of containment Because of elevaling Aux Building Radiation levels, the acting Emergency Director has classified the event as a Site Emergency The following actions have hben cnitiated completed
- Classification has heen made
- TSCiOSC is being manned
- NARs and ENS notifications htave been rmade
- ERDS has been activiated The NEXT action for onsite personnel .vll be to perform a Ste t' per prOcedure !2,
(') (2)
- a. Eva cuatiof EP-AA. 113 Personnel Protect we Actions
- b. Assembly EP-AA- 114 Notifications C. Assemrbly EP-AA-1 13 Personnel Protective Actio 1s
'dj Eva c-ua~t-o-n t-_ _
I [l4Eauto PA-14 Notifications Li
_SW bate-OrS i IC J txam Leve l - taogn-'veLOYI , pplcat-of - Facility: Braidwood -fmDatJ 7/1902)
WEO4G114 1 2114 ROVlu :-!a] 25 S Vs:
S on:]
F rPE 2O "1 GOGrorou p .ROfr l -J u Utlo T s LOCA Outside Containment E04 Knowledge of system status cnteria which require the notification of plant personnel.
°Jt (C) Correct - the assembly of personnel is the next action to be performed (before the evacuation). This is accomplished under EP-AA-1 13 for onsite personnel (A) Incorrect - assembly must be before evacuation to give a full accounting of all onsite personnel (B) w ;--uw
- Os AA;ovvA first RefeRenceTitb I Faility Rerece Nu r j hferenc on ]Page No. Rk ntLOn Nne Personnel Protective Actions F PiMAA 113 _ _l Attach485 13. 155 J 2 - _
I F _ _ _
__IiLI
__ JI r_ __
_Us _ _D
___r~L__ rn__ .a __r.
II *ll
__ _md_
_ __ -- _ti[ I i daReqkeferExaiato }J_ -- -__
8 0ioSurc lNew ljQueton odlflcuon M~ethod: J Used During Tr inhgProgra l
=--.
- ____I il I
ConwmentType loirrnt F -J 7-- __ - - - -. - ..
_ _7 _- _
Reviewis;Complete
'Supervisory ii Facility NRC 51
Question Topic O(A O).,t.
L )( ( ra r enr ai wo I S18835 SI PUMps to Cokb Lkq l .toltior' Vile. remain While perlormirig 1B..(.A 1 2 LOuA ( )utside Containnent- under .%hat corlition would closed after being rerositioned)
- a. RCS pressure ,s increasirc;
- b. SI purnp discharge pressure is increasing
- c. Pressurizer level is decreas ng
- d. CETC temperatures are decreasing ExamDate: 7119/02 Answer a j Exam Level B J CognvLive Levl [IApplication Facility: Braidwood KA-; [04K302 - EK3 2 iROsVa: _4 3j iSRO Value: 4 [Secuon: EPEJ RO Group:l 2A SRO Group: I l E04 SyjtemlEvojutlon Title LOCA Outside Containment iKA Staent: owledge of the reasons for the following responses as they apply to LOCA Outside Containment:
j Outside Containment) l Normal abnomal and emergency operating procedures associated with (LOCA increase. (B.C,D) are notoptions F (A) Correct - as stated in the procedure 1BwCA-1 2 as the leak is isolated with an RCS pressure as given in the procedure efernce
_Ri7 TMtb 'umr_ ]6forence Section _ }I PageNo. Rioni LOCA Outsid Containment (CA) j 1BwCA12 _ _ NOTE JFAWOj _ __
__ ul7 Emrin _Kon aterial Requiddfor Examnination_ K - -
_fodlolc ction Metnod: - Ued During Training-Pronrarn l Idjiii6 Soirce Comnments Reviews Complet.
ommientTypej Comment __ _ __ _ _ __ _
- Supervisory r-Facility NRC
Question Topic P'nsa'i:.',rd -*-nal Snock The following conditions exoit Or,1 11
- Steam generator 1A tube mJptL.'e ras occ jrred
- Crew is performing the irtial Ri S cooldo nri step of 1B/ EP-3 "Sleinm Goner .0 )r T be R. Iptkjre"
- All RCP's are OFF
- Loop 1A Tc indicates 180 F The STA has reported an ORANDE Dath Di RCS Integrity The Unit Supervisor slhou'k I because (2)
(1)!2
- a. Remain in 1BwEP-3 uintil tWe second Cold injection Pialer is ccoling LoOD 1A RCS depressurization is cc-,vlete Twiold
- b. Immediately transition to tB..FR-P 1 A severe chal enge exiss to the CSF
'Response to Imminent PTS
- c. Transition to 1BwFR-P 1 as soon as Cooldown in 1BwEP-3 takes priority the initial cooldown is comp ete over 1BwFR-P t ld Remain in 1BwEP-3 until the approprate An RCP will be started in 1BwEP-3
__ ISlITR rcni 1vnrnri rp LSs-J-mIrAed _ - -- -- -
Exam Level C gSnitiv Level I Apptca7on l9Facilt: ExamDas L 7/1902j 2Bradwoo_
] [OWE068A202 EA2,2 ROValuc: 35 OValueVaj1 41 Section. j -PEj j SROGroup:'
tOGrou][ J 1 pyotnJEvoluti _tl__e Pressurized Thermal Shock _ E08 W Ability fo determine and interpret the following as they apply to Pressurized Thermal Shock:
Adherence to appropriate procedures and operabon within the limitations in the facility's license and amendments.
f(A) correct - per 1BwEP-3 Caution pnor to step 6 and Note prior to step 28 (B) Incorrect - same caution states NOT to do FR-P. 1 at
_this time. (C) Incorrect - same caution states to wait until completion of step 28 (D) Incorrect - caution say wait until step 28. not LRefere nce TTle I Facility Relerence Ntinber Reference Sction ] LPae NO Rvsion LO. Number lS jBwEP3__ 'step6. 28 10.36 l 00WO
_ _ -__-Z -__--- Z _ I !&! 1 _ J Pblrial Required for Examination rsto Source: New - _
-= uestlon Modification Method: j j Used During TraIning Program
_ _suii_Source-C--- __n ----- - - - - - - -_ _ .
K- . - _ _ _ __ _ _ __ _- ____
CornmntTy-pe ] nc nt - -'--.- - -- Revies Complete
-SROJ sem nvtof plant conditions, procedure selection j Peer
. - = - Supervisory Facility NRC G3
RO SkvScraie SRO SRiraw l O SiteMlEvolUtion List SRO SseinflEvohition List l Outiie Chalges Question Topic Pressunzed Thermal Shock Which of the follo:, nq reflects the intenl of the major actions perdormed in I B-FR-P I 'Response to Immn ent Press L.1:ed Thermal Shock-9
- c. Increase RCS cooldown rate and decrease RCS pressure IdJ! Increase RCS cooddown rate and Increase RCS pressure ElxamLv CoInitie Levei] Memory ;jFcility:JI FBraidwood Exaimrtte 7119,02j
_Answ er Ia a m----e--B--- ---
Ejk l00WE08K302 J EK3.2 [RV *1 36ISROValUej O Se n: jP jROfi-ucd j S IIj ROt: l J Wf Tii Pressunzed Thermal Shock 'E08
" 8iaterl;i; l Knowledge of the reasons for the following responses as they apply to Pressunized Thermal Shock-Normal, abnormal and emergency operabing procedures associated with (Pressurized Thermal Shock).
istbii of llkC.D) incorrect - increasing the cooldown rate increases the thermal stresses. (B) incorrect, increasing RCS pressure increases the Iiie: ' I stresses (A) Correct - reduces thermal and pressure stresses, per 1BwFR P.1 I Refernce Tltbo L Facitiy Reference Nunier7 31ictio [il LNmber ]
Responseto Imminent PTS ll1BwFR-P. 1 __l 3-22 AWO l_l_
Response to Imminent PTS j Background Document P-i 1 - --- -- i
_:_____ _ =___ _ __ __ ___i= =
Requld for Exunination ui I__
iatlon Source Facility Exam Bank l eson odiirin Meghod: Editorially Modified ] fmed During Traing Pro Quesion SOrce Comments 1 2001 Bwd NRC IWA-I
[penti omen__ --
0!1"sorv IFacilty I I iNRC
Question Topic Na)lLJrl .rculation Opexa. ns a loss of tc.r :.d cooiant flow If operated witthin TS limits, a I 0' the tolio. ing preclude thre hot fuel rod in the core trom uncergoing DNB during accident EXCEPT
- a. OPTR
- b. FO,
- c. FNdH
- d. DNBR
'mLovell IS Level j Faclllty: Braidwood Em 7 1902 n c j lCognitive KA-1 OOWE09A202 J EA2 2 RO Value 3Mj LSRO Value: j [ s Section:I rE j RO Group: 'j SROGroup: _ 1J E09 jSybmrlEvolutbln Tiftb] Natural Circulation Operations F Slatnj] Ability to determine and interpret the following as they apply to Natural Circulation Operations:
Adherence to appropiate procedures and operation within the limitations in the facility's license and amendments.
DNBR 3.2.5 (C) correct (A.B,D) incorrect - per TS basis each protects against DNB on loss of forced flow. FQz 3.2.1, OPTR 3.2.4.
response - does not predude DNB on a loss of flow accident. TS Basis 3.2.2
] Number 3j ,,J w s.,, @ ~-JD
_w -- 7 u Pl NFo.l]itm o. 0
_ecSpecs___ JBasis 32.1.32.2.3.4.3.2.5 7 J 122.23.01f Ii1 Spc ___==_-_----- -.--- - ------ -- - ---- ------ -[- !
_.m _..
.__~.~ _ -. __ _
elRquked for Examination - ____ -
New I Qution _od___ka_ - _ ] Used DurinigTraining Program Comment~y_. ., ___ _ ___
.omnn kiustai Sourc-dolifil lnits Commwnt TyiS i Co Reviews Complete I SRO l Tech Spec and Basis knowledge rvhr POWSup I lFacility NRC
Question Topic Nitural CiriUlation O;-erations Which (f the.oilcoiiog describes why it is rnportant to run CRDM fans woer periorni rg a natural circulation cooldoril
- a. Provides the heat remo .. l mechan sm for the vessel head area
- b. Aids in natUral circulation flow thIoigh the RCS vessel head region
- c. Prevents er'atic indication of SR instruments
- d. Aids in inatlral circulation flow through the RCS
- ,nswcrja Exam Level IBel - __ l Facility
- Braidwood j ExamDate: - 7/19/02 jKA:J [ootvEo9K2o2 I EK2 2 ROValue: 3.6 SROValue:j [39 Section: l EPE J ROGroup it SROGroup Ij SystenmdEvolution Title NaturalCircuiation Operations = _=___ __, E09 KU btement:, Knowledge of the interrelations between Natural Circulation Operations and the following:
Facility's heat removal systems, including primary coolant, emergency coolant. the decay heat removal systems. and relations between the proper operation of these systems to the operation of the facility.
W." ' Of IM[CRDM fans cool the upper head region that may not be cooled by natural circulation flow. Rx Cavity vent fans provide cooling to the Reference Title - rFaciW Reeence Numer eren Section j =k a ol r.O. Reviso Nume r lEP-Series LP -3 J 11-EP-XL-01 Vll j38 J 13 13 1 lNatural Circulation Cooldown iBwEPES02 Step NO 14 j IWOG1Cj_
-- -_- _ = - 1 - - _ -- _- i - -J-- J_ - ---
Iatertal Required for aminaton _ j
'Question Souce [acility Exam Bank Modificationt Me Method: Diret From Source -jUsed During Training Program, Question Source Comments 1999 Bwd NRC
_- --- _- ___ _ 1 Comment Type Comment Reviews Complete
,_______ - 1 Peer I I h .supervisory:
Facility NRC
Question Topic NaturrlI (Crcutation dthrSteam V d wil .tvhoutRVLIS The followving conditions exist on Unit 1 1BwEP ES-0 4 'Natural (CIrcLulation Cooldown w 'h Steam Vo (i in Vosse taoott RVLIS) Unit 1 is in progress
- RCS Temperature is 450 F
- RCS Pressure is 800 psig
- RVLIS is NOT available
- Chfarging and letdown floas are matciled With RVLIS NOT available to monitor for void growth in the vessel. which of the folowing combined indications can be used to verify the presence of a void 9hen letdown flow is increased ' charging flo.. 2 RCS pr( ssure will t1 and Pressurizer ,Il
.%el 12)
( 1) (2)
- a. In-, ease lhrease
- b. Inicrease Decrease
- c. Decrease Decrease iL -nprxrpas - Incrpras- _ _ _
Antr id Exam Level R Cognitive Level Application j Facility: IBraidwood ExamDate: I 7/19/02 f60WE1012. J EA1.2 ROVals: 1 I 3.6 LSROVaIue: rl .c n EPE ROGroup j 11;SROGroup: il EvotrJfJvion TitMe Natural Circulation with Steam Void in Vessel with/without RVLIS E10
_ _ __ J I l Ability to operate and / or monitor the following as they apply to Natural Circulation with Steam Void in Vessel with/without RVLIS I Operating behavior characteristics of the facility.
- Ion d I (RD) ~Correct - rapidly increasing pressurizer level during the RCS depressurizabon is a sign that voids are forming in the pnmary
__ -__, system. Pressure decreases, fluid flashes to steam displacing pzr level (ASB) incorrect - pressure decreases as inventory is I-' cv c v_ Y ___' ~_Y' _ _ _ __ _____ ___ _ __ =
Rohrence Title Facility Reference Number i Reference Section Pge No Revision LO. Number l Nat rc Cooldown w/o RVLIS j1BwEPES-0.4 -- 117 jNotestep8 1AWOG j Background Documents __ BwEPES-0.4 J-SIep8 33
-j J 1C 7r _ ,
tR~IaRequired for Examination ; -
Qeistion Sourc e- Ne - -uas-- oModicaion Method: Used During TraIning Program
!__ __e New - -_--- __ I___ _ _ _---------j- - _
j tion Source Comments Comment Typ I Comnent Reviews Complete r Peerj Supervisory Facility NRC Si
Question Topic Soar (.rr eratrc Overpressure The folloA; iond tions tx st on Unit 1
- A spurious closure of a I %1SIVs ^ccurred while operating at 100`;, power
- The reactor .%as manally tripped by the operators and immediate actions of t B.E P-0 were perforrmled
- Recovery operations a'e in progress utilizing 1BvEP ES-0 1. Reactor Trip Response-
- The STA has identified a YELLOW path overpressure condition on lC SG with pressure at 124 ' psi;
- Checking 1PM04J there is no steam flow indicated on the 1C steam generator All other steamn generators and plant safety systems functioned as designed
- During subsequent repairs the unit has been holding in Mode 3 for the past 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> The rcoiiditioi of the tC steam generator is reportable to the NRC because
- a. The plart exceeded a safety hmit
- b. Chilleriqes occurred to safety valves
- c. A loss of tvo fission product barriers is imminent
- d. The plant is in a condition prohibited by tech specs inswer _Exam_. ! _ Level_
_Braidwood Cognitive Level lApplication Facility: .
J_ a ExamDate: ,
7/19 02 KA: 00WE13G430 2430 *tOVait: F2 T LRoValue: 36 Section: EPE RO Group:! [ 3 SRO Group:' 31 SystemnEvolution Title rSteam Generator Overpressure E1 tae_ _ .ent_ ___
KjL Statement: -- ____-_--_ -_ _____________________
I Knowledge of which events related to system operations/status should be reported to outside anenreie A
I*=-r----- ---
jtI (A) Incorrect - the reportable safety limits are for pnmary system power level and pressure only. (B) Safety valves are only the Pzr safety valves, not the SG safety valves (C) Incorrect - loss of 2 fission product barriers would result in a Site Emergency which we ww< 11t A.~~~~~~~~~~~~~~~~ - ... .- __ . F .....
_.-_._.__v __ I I _._...
abovabvethe_
Ihe l litsetpoint n ofalM all Malsafety vatve which are inoperable. _ --
_R=f_ - _ Reference _ Ti e__ _ __ 7 =l'FacltyRnc
_ _ =N=_ Number 1tReference
_ _ Section _ = =i_ _4PagNo.] = I_ Revoion_ tO.Number] r
l[Functional Restoration proc SG Overpress FBwFR H2 _ jjlAW0G_ Ji FRH2background document - J FR-H2 j FR-H.2 r-- -
r-----_
{Exeoneportability Manual _r~
jFLS-AA-11lo _jSAF 1 11 _= ___l J. - - - ii~__
1_aterlai Required for Examination ri __ __ __ _____ -_---=___
piitlon Sourco JNew j estlon MoificationMh Training Program iuetion Source Comments1 Ir - -
ICommrnntType
-1 -- - - r___
Comment I ____ _ ___T_ __ _ _______
77 1 --
{9eiwsCornplete C - _
___ __ __ -- . -_: - - - __ - - i- _= _ =:-- = - -i
'Peer I
- ---=
Supervisory Ii I-I Facility NRC se
Question Topic Steami Generator Oerpressuire The foliONing sequenzce of events has occurred on Unit 1
- React:or has been manually tripped due to a secondary system malfurc icn
- 18vEP-0 has been performed and a transition made to 1BewEP ES-0 1. Reactor TPip Response
- The STA has identified a YELLOW path on the Heat Sink Status Tree for steam generator pressure
- The crew has entered 1B-oFR-H 2. -Response to Steam Generator Overpressure
- The crew is preparing to dumnp steamn from the affected steam generator
- The US reads a CAUTION that does not allow releasing stearn from a S( with a narrow range level of greater than £j3 Why shouldnt the crew clump steam from the affected SG if NR le-el is >93
- a. May cause an uncontrolled radiation release since it is likely that the sVeam generator is ruptured
- b. May result in two phase flow and water haninier potentially damnaginq pipes and valves C. Will be ineffective in lo ering SG pressure since the SG %%ateris likely subcooled
- d. Wilt cause a rapid pressure drop in the RCS potentialty resulting in a safety injection r32 nswer Ib I Exam Level IBiC j nitiveLevel Memory Facility: [9raidwood j ExamDa:
i i 7/19/02
[00WE13K202 I EK2,2 OValueIl 3 j SROValue:J Section: jEPE ROGroup: l~ SRO Group:1 31 Item/ EvolutibonTTti t Steam Generator Overpressure W -Sbatemnt:! Knowledge of the interrelations between Steam Generator Overpressure and the following:
Facility's heat removal systems. including primary coolant. emergency coolant, the decay heat removal systems, and relations
__ between the proper operation of these systems to the operation of the facility.
ati oi4 F(B) Correct - per FR-H series background documents. (A) Incorrect - no indications are present that would suspect a SGTR had IE 7 A
. - _ .ef, _c , _
1 occurred. (C) incorrect - at 1235# and RCS Tave post trip. opening the PORV or Steam Dumps will release steam. (0) Incorrect -
Fcility Ri~3 Ro Numl~ Reftrene :il N~ tionNo.
I
[Revisilon 'LO. Number~
Response to SG Overpressure III1BwFR-H 1 R_ _ ____
Background Documents J[FR-H2
- - --- ~ iICaution
_ILI___
_ J1
- -- f _
,, -- - - . I_____' - 1-- -=_______
R Reqlduired for Examination I I utoni sOWr-e ther Facility __ aQesion Modifi n Method: _ Used During Traning gram stion Source Comnments 12001 Praine Island NRC Fomment Type l 1Comment 1 uRfvhwr - - -
I _- - I . - Supervisory
!Facility NRC
Question Topic High Cr-,- ,inrnent Pressure While performing actions of 1BAFR-Z 1 Response to High Containment Pressure-. what steps are taken to lintt tie peik presire r Ie containment in the event one of the steam generators is faulted'
- a. All four RCFCs are started in Cast Speed upon entry to lBwFR-Z 1
- b. Feed Flow is isolated to any steam generator that is depressurizing in an uncontrol!ed manner
- c. Aux Feedwater Flc,%to alt steam generators is throttled down to 45 gpm per steam cenerator
- d. Alt steam generators are allo.ved to completely depressurize before exiting 1BwFR-Z 1 J Exam Level insweri B Cogntive Level Cr° prehension ExamDat fA: 00WE14K202 EK2.2 ROValue hr 3 4J ,SROV a l 381 [S ctlon:J ! EPEJ O Group: 1 rj SRO Group: 9 S;ystemlEvoltlo TTle 1 Iigh Containment Pressure _J E14 H ASt tilj1 Knowledge of the interrelations between High Containment Pressure and the following:
Facility's heat removal systems. including primary coolant, emergency coolant, the decay heat removal systems. and relatons between the proper operation of these systems to the operation of the facility.
. - (B) Correct per step 6 of FR-Z. 1. (A) incorrect - RCFCs are never run in fast speed in adverse containment conditions to protect are the fans (C) incorrect - AFW is only throttled to 45 gpm if all steam generators are faulted. (D) incorrect - all steam generators IIf-ICV. .4* J. I.' -, . V -A- Z.- *I.
Ree -rnce Title __ rV Facilt RnXNimAber_ Sectlonj ' Paga bo. fRvislon1 CO. numbe i 6ferenc tesponseto High Cnmt Pressure j l_1BwFR-Z. 1 l9 _j
[-_____ ]Bwr-Z -- 9-1- --- __ 9 1 J AOJ ___
__ _ _ _ .__j.
wrblsI Required for Examinatin ] - - -
~SUbn SoiirW [;ev -e __ ]2 Un lldlio ____ho V __ uD~g Tralning Program]1 Question Source Comments CommentType] Comment --- ---- - - - -- - 1 ~ReviwsComplet ormn -- - 1 Poerrj-t i
_ - J F-- - __ _--- - -- - ----- - --.----------- ----- -- - - -- - ----- --
.: I - - . .. . . _ ___ _ [Superv- -- '-isr
_ __ Facility NRC c0
Question Topic High ContaiInment Pressure 1BwCA-1 1 Loss of Emergency Coolant Recirculaton-. is in progress .%nen a RED path is identified for containmeri pres',iiwr ZQvR-
-Response to High Containment Pressure. is entered immediately and Containment isolation is verified The operaeors thrern oi . .ne the Cr-mtainment spray system according to the direct urns found in 1BwCA-1 I inseaa .-' 'BwFR Z I Under these conditions IBwCA- I akesprecedence over IBvFR-Z 1 because the 1BwCA-1 1 pump operatino citora
- a. Ensure .hat the maximum hear removal system capacity is used *o reduce containment pressure
- b. Are more restrictive ensuring continuolis containment spray ss'em operation to reduce containment pressure
- c. Are less restrictive permittirg reduced containment spray operation to conserve RWST water
- d. i Provide a more rapid mearns of verifying automatic actuation of the containment spray system lAnswer [lC ! B
[LV I Cognitive Level [Appication J jFacilty: JBraidwood J ExamDate: j 7i' /0211 i ; OWE114K302 R u: S u jPE #ROGroup: i1 SRO Group: 21
'SysteEvoluton Title [ HighContainment Pressure - E14 lKA Stament: Knowledge of the reasons for the following responses as they apply to High Containment Pressure: _ __ __l Normal. abnormal and emergency operating procedures associated with (High Containment Pressure).
tn OofOI (C) Correct - spray operation requirements are relaxed to allow conservation of RWST water inventory (A) incorrect - CS is not maximized but reduced (B) incorrect - 1.1 criteria is less restrictive. allowing no CS pumps if all RCFCs are available and running in LO Num I _
_oI_ ____vison
__= _i La Refers_
R _tc _=_be _ ci -=_ -]-'r~----
1BwFR-Z.1 :Caution l Response to High Containment Pressure ossofEmergencyCoolantRecirculation BwCA-1s1 tep9-table !8 ! 100 _
all Required
_. _for_ Examination
_ _ a.in_ ._ j______ _ _-_
QubnSuroJ Question Source Comnients
[Facility Exam Bank I
- lJ n Nlodicton Mtethod: Editonally Modified ] [Used During Training Program7 j
Oooniliet Tpe Lwfr" Reviews Complete
~~ t Type Comient -0 li'Peeor
- - - - --- iIPr I_ _ _ --- --
r- I Supervisory
- Facility jl ~ NRC
Question Topic Containwent Flooding, A large break LOCA has Occurred on Unit 1 The crewv is currently performing , eps in lBwEP-1 'Loss ot Reajctor of Sec (.;rnt-Coot;lr a The following conditions existed when the STA made his initial scan of the Status T-ees
- Pressurizer lewel .vas 0".
Containment spray had automatically actuated Crnft pressure was I2 ps ( arid cdecreasing C
- Containment rad monitors 1RT-ARO20 and 1RT-AR021 were in ALAR'.1
- Containment floor .water le.el indicated 65 inches Which of the follov.,ng proced.,-es must be entered to address the above conlainment conditions?
- a. 1BwFR-Z 1 Respcrse to High Containmenit Pressure
- b. 1BwFR-Z 2 Response to Containmen! Flooding
- c. IBwFR-Z 3 Response to High Conlainment Radiation Level
- d. lBwFR-l 2 Response to Low Pressurizer Level 7
Answer b i Cognitive C L vl ication PacllltY:jlBraidwood
[ j E1ameate: - /l 9 /O2 jj
'KA: [00WE15A201i EA2 1 ROValue: 27 lSRO Value: I 32 Section: i 1EPE jRO Group: __3; SRO Group 3j m/Evdlutbcn Tyst nt, Fontainment Flooding J E15 kA sttateentj Ability to determine and interpret the following as they apply to Containment Floodingl Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
[ lation o (A) Incorect - cnmt pressure is <20 psig and not required to be identified for entry by the STA. (B) Correct - flooding entry pt is 64 hiwerw inches. This is an ORANGE endpoint and the highest in the conditions present. (C) Incorrect - Rad monitors in ALARM is a
-- _ece
__ _e*me Nme Section ,Pa NO.i LRio~lwfl NUmb Containment /Inventory Status Trees j BwST-S and 6 V -Jwog 1C If_- --- ----- ----- F---=----i-- - -- ---- =-Q -- -- - r~------
_J________J
- MterbiRequiredforExamination , 1BwST-5ContainmentStatusTree S3ource
- Facility Exam Bank u _thod:Modi o fSignifcantty Modifiedc Jd Durlng Training PmoiVr-r--- -_--_-___
nuastion Source Comments 2001 Bwd NRC -
l ent Type j Comment Reviews Compt r--- :: -- -j_-- -= - _- __ -: - Peer=:-
- ---~
I- J -- - ., p Survisory, Facility NRC (p2-
Question Topic Higjh Coro!amniemrt RadCation The following conditions exlsl on Urit 1
- A sniall break RCS LOCA occuored 45 minutes ago
- The reactor was successfully tripped and Si actuated
- RCS pressure is 900 psig and Increasing slowly
- RCS temperature is 500'F and decreasing slowly 25
- Pzr level is % and increasing slowly
- Containment pressure is 4 psig. decreasing slowly troam a peak pressure of 22 2Sig
- Containment radiation levels are steady at 2 6E5 R,"r
- All S'Gs are intact with NR levels at 27, and increasing slowly
- The operating crew has performed all applicable steps of 1BwEP-0 and nave 1t insitioned to 1BwEP-1 Loss of Reactor or Secondxr, Cioolant Which of the following statements is true concerniig the current plant conditioIs'
- a. Total Aux Feed Flow may be throttled back to less than 500 gpin to reduce RCS cooldown effects
- b. Containment Spray pumps may nowv be stopped at any lime deemed apprcnriate to conserve RWST invenlo'-y
- c. RCS subcooling is acceptable and Sould allow for St termination if all other parameters are met
_dj lPzr levelwould require Si be immediately renibiated if it had been previously terminated - -
Fr/19/02; I------- -
- -- -- L: 7= -
nswerrF Exam L o tveLevel Alpiplication Fility: Braidwood ExamDat VWa vei B Co _n __ApFI7 1/0-Fw66 V i e]ction: EPE I 'AOGrouo] r2l SROGroup:' i 21 High Containment Radiation =_ E16
,SymiEvolutlo'thh d sA9taitiY]e Ability to operate and / or monitor the following as they apply to High Containment Radiabon _ J Components, and functions of control and safety systems. including instrumentation signals. interlocks, failure modes. and automatic and manual features. _
jdAdverse containment condibons exit due to the high rad levels (>1E5 r/hr). (A) incorrect- requires SG evels between 3150.
(B) l
- j incorrect - requires run time of >2 hours. (C) incorrect - 500'F requires 950psig adverse cnmt. (D) Correct - Pzr level is required to -
Reference Title I Facility Reference Number j f.ferhnce Section Page No. Revision L.O Number
[oss Of Reactor or Secondary Coolant EP___ 1BwEP-1 _ _
6 j[ rSsteps 3.6.7 j0 j 1 wo 1l_ =r-- - z -- -- _ L-i __---- -jL Maerial Required for Examination - Figure 1BwEP 1-1 RCS Subcooling Margin .D _.
ring . _
j
_ ____. I _ _ ___ _ _
Sowce New = j _ "
f Method Used During Training Program
_ __ _el t _ _._ __ __ _._____
Question Source Comments l __
Commnlt Type Comme nt i Revlews 1 ComplhteI Supervisory Facility NRC
Question Topic Pte-skirizer Level Control Systenl' PZR LCS~
Which of the fol lo.%ing PreOssuIrizer level :riann els is N07 densi ty compen)Satedj ni1a61i t read Ia wer than actmi!. evel a I no al o:~ era tinrg temperature and pressure?
- a. LT-459
- b. LT-460 C. LT-461
- d. LT-462 Anwrd jExam Level i jR- CgiieLvl Mmr Facility: Braidwood JExamDate: _ - 7/1902~
9Ulli [O11OOOK4O3 K4.03 ~ 11O Value:: 26SOVaIUe: 29~ Section: ISYS ROGroup: 2j SOGop: _2 L~yatem/EvolutionTftlie Pressurizer Level Control System -__ ___ 1
~5~Satemnt~lKnowledge of Pressunizer Level Control System design feature(s) and or interiock(s) which provide for the following_________
IDensity compensation of PZR level ___ ___________ ___
106 UonaiiOfj[T-462 is not density compensated or calibrated to read accurately at pressunizer temperatures of -680'F. (0) is correct.
LI ' Refemnlie Thite iY1 FiaciyReftroh eNumber ] 9F6eeiRiITO unbo Pressurizer LP _ _ i r ~ u _ __ _ _ _ _ _ _ _ _ I__
Fl5 __ _
MatrlaRequired forExamination - __ - i
- Exam Bank jL~uestion Mdifiaton MeNo: Editorially Modified jUe uigTann rga~
~~u r e c~-mme t s _ _ _ _ _ _ _ _ _ - - _ _ _- - -- - -- - - - -_ _
,tomnmne ype1 Conment -oplt
________ K~eri
- - - '!Supervisoy
____ ____Facility I
- 'NRC
Question Topic Prtssu'izer ,e.el Control Systemn (PZR LCS)
- What single or coibiiil ion of P-,fssUrizer Level Channels. if failed. w Ii equlire xi a!ditional Tech Spec entry for Post Accident Moniitorirng I PAM)
Instrumentation. LCO 3 3 3)
- a. LT-459 alone
- b. L T-459 and t T-460
- c. LT-460 and LT-462
- d. LT-462 alone iLse I. b - - - - -riwo -- Failty
_~ `1-Exam Levl j Cognitive Level jFll Braidwood j ExamDate: I 7 9 1 2 FnF60SYS5
~M:OFGroup: ale~t 3j;SectinGroup KA: 01100OK605 K6.05 ROValue:1 ROGroup3 SRO Group: !
Sl-tlEvdlullon Title lPressunzer Level Control System _ __ __ _ _ _ J O1 X l Knowledge of the effect of a loss or malfunction on the following will have on the Pressurizer Level Control System: I Function of PZR level gauges as postaccident monitors __
of_ TS 3.3.3 requires 2 channels operable. LT-459. LT-460 and LT-461 are used for PAM intrumention. 2 of these 3 channels
- i-;inoperable will require entry into Conditon B for PAM 3.3.3. (B) is correct e
- nce Title PaS weN&ilerj Ka [Reil LAO WtOuber lTech Specs __ JILCO333 _J lnst F33.3-1 Am98 _ J FAccdent Monitonng Inst Monthly [TwOSR 3 3 3 a MateRi qulRrd for Examination -
-ueation Modiastion Method: _ J_
__JF d During TrainingProgra tln Sotrce Comments
,Commnt Typel Comm ent ~ I Fl
-~ -- . -- !-.-------------
_ - _1 lReviws Complete I ,P r'
{~ Jr------------- .-.- ------------------- --- ____J
, Supervsory I Facility I I
I NRC
RO SkyScrawoI SRO Skncrrl RO SvvtemEvolitilon List I SRO Svstvoluon L.st Outline Changes l 2 i-__
Question Topic Reactor Protection System Given the following plant conditions on Unit 1
- The reactor was at full power with all systems in a normal, automatic lineup
. The reactor tripped on a LO-2 S/G narrow range level condition
- Reactor tnp breaker B (RTBI did NOT open as expected With NO operator action. the steam dumps will open on a signal from the (1) controller and will conltol Tave a (21
- 11) (2)
- a. Plant trip 557F
- b. Load reject 557 F C. Load reject 560°F
- d. Plant trip 560°F AAUrCJ "xmLVol [ _
11~onivs Level] [Application J_ ___
aI~:FErailwood
__ =__ < ~
j~crrDats: I 7/19/02J 012000K303 IK3.03 ;ROVaIu.ej 3V VI uaS,js sectio: I SYS LRGrup: 2 SROG2p Evenfolni R9eactor Protecton System l 012 A lte Knowledge of the effect that a loss or malfuncbon of the Reactor Protecton System will have on the following JRTAarms the steam dumps in the plant trip mode. (AD)are incorrectasdumps will onlybearmed for the load rejecbon (>10%)
- Temperatui e will be controlled within a 3-F deadband - in this case from no load Tave. (C) isthen correct. (B) Is incorrect El T - F Rt tiiibore N e rence 1etion11,p Nol R 111ii Operator Big Notes JIMS-4 l_JIJi6_Jl_
____ ~-- 6- j 711---
71v
-- r--_ _ --- -___ -_
I7Jf
,_ _ _ ___ - _ I
___ _ ___ __LF__ _IK .9 .1Ti "awlia R"W d forEiam!fon~ I 1 Ouso_ n Sour:_j Faality Exam Bank j Puestlon dll 11100thod: Direct From Source J Ing Training Program]
tn Soto nlmeni I Comment r-- -
e
-ii Comen 7-:--r
_ _=ReVis
-----.- =---
_C
.-- l--- ,,.
F-aclty Supervisory NRC y
omPlette 1
Question Topic Reacr f Prots tiO'i System Which of the following reactor protection system trips serves as a BACK-UP to the Power Range Ncjt'on Flux Hiqh trIp nrid is d(110d to ensoire that the allowable heat generation rate (kwfI of the fuel is NOT exceeded?
- a. OTdT
- b. OPdT
- c. Pzr low pressure
- d. RCS low flow i w rj J LExanrv.l ! IB i ,Coogniti Level rMemory J Facility: Braidwood j ExamDat: 1i 7119/02; K j iO0052 J K5.02 ROValue: l31- SROV lue j3. ISection:j lSYS RO Group:; 21 SRO Group:' 2 ISystenEvolutlon Title Reactor Protecton System 0012 AASa n Knowledge of the operational implicabons of the following concepts as they apply to the Reactor Protection System :
Power density Per TS 3.3.1 - basis (B) is only correct response
- I F4iclkeneelleenddNe d PagieN] _ # . Nuitj Tech Specs JBasis jlBB3.31 j j l24 __I
=_ r- -~ -- ____
____ _ _ __ ___ ___ __ _ _ . J-_ .
, ebl Required for Examhiation - _ ___ _
i _- _
[jlj[ ~ ~ to _ JUiiabiudngj raiinln gPrograiln p,,,r-ew
- urceCormm Son8 nts I -r-(~~ - -- - - ~---- ~ ~~
Type; omment 1 'Revies Compbe r-7 ~ -- ~1-------- ----- ---- = J~-=-Peer---= L_
_J _ _ _ __ _ -- - --
r-____ _________ _____ ______ =Supervisory
_ _ -___ - -_-_--_-_-_--___ -__--_- _*_- - - ' Facility iNRC
- . i
Question Topic Ergirleered Safety Features Actuation System (ESFAS)
The followirg conditions exist on Unit 1 A RCS LOCA has occurred
- Safety Injection and all ESFAS equipment has actuatec and is functioninq is ieslqned
- The Emergency Directo' has declared an ALERT cond ion exists
- The crew is performing the actions of 1BwEP ES-1 2. Post LOCA Cooldoi.r i-id Depressurization
- No CSF higher than YELLOW is in effect
- Annunciator 1-6-B7. RWST LEVEL LO has just alarmed VWihich of the 'cllowing actions should be taken'
- a. A Site Evacuation should be ordered AND the people directed to assemntle at the New Training Building
- b. A plart announcement should be made warning personnel to restrict entry ,nto the Aux Building due to poten'ial high radiation
- c. The event should be reclassified as a General Emergency AND the NRC State and local governments notified immediately
- d. Protective Action Recommendations (PARs) determined AND State and local governments notified within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> following evaluation lAnswerlb I am Level i Cognitive Level Comprehens9on Facility: lBraiwood ExamDate: 7
/19'02j k r---3_0 2.1.14 ROValu el 25 `SROValue: 331 Secton:j [SYS OGroup: I LSROGrop:! 1 T_ ngineered Safety Features Actuabon System = = 013 Sftaime nt: _
lKnowvledge of system status criteria which require the notification of plant personnel.
L
[jianaion ofr 1(A) Incorrect - No radiological safety hazzard warrenting evacuabon is in progress. (B) Correct - Switchover to recirc l .ll high rad levels in the aux building. (C) Incorrect - No General Emergency conditions have been met. (D) Inconrect may cause
- PARs are only
__ C 9 Ug .sV -: SV,~ _____ --- _ _______ ..--
_ beir_*
___r __ _8 Srection PageNo. Revison] ONw Transfer to cold leg recirc 1BwEP ES-1.2 l CAUTION
- 0 100 j _
inerang tto EmrencyPan FGSEP-Braiod Annex 'Initiating Conditions 34F5 6 iJ rEmerg Classiications & PARs JFEP-AA-11i116 -
_1 _ _
Required for Emmination - - - -~- _ _ _-_- _
_Soutrce tl_herf acility J Qe n Moi ton Meithod: [Editonally Modfied Used DuringTrainig P m 4uetion Source Comimants 2001 Prairie Island NRC pommen n Type' comment i Review Complete
~-~-1r---------__ _ _ ___
Peerm@.
-- r ---
--L- -= -- ==l
______ Supervisory Facility NRC
Question Topic E ini r1erd Safety Features ActLation System (ESFAS)
Unit 2 is presently at 90% po.emf and shutting down due lo an extended loss of Instrinent Bus 214 All systems <i e in ,itormatic whenla loss ot reactor coolant occurs When pressunzer pressure reaches 1829 psig on 24 channels which of the following .ill occursn
- a. Automatic SI will occur Train A ECCS equipment will automatically starn Train B ECCS equipment must be manually started
- b. Automatic SI will NOT occur Train A and Train B ECCS equipment .il autofrat'cally start when SI is manually actuated C.. Automatic SI will occur Train A and Train B ECCS equipmrent will automnatical.y start when SlI s autornatically actuited d., Automatic SI will NOT occLr Train A ECCS equipment must be manually started Train B ECCS equipment cannot be started nswer ra __
ExamLevel
=__ : _.
R !__Cogniftive Level
__=__
Wplication
[I l_Facillty FBraidwood
-Exa -ate:]
7/19/0
_Li
,A: 013000K201 K2 01 ROValt - 361 *kROVa lue: 38 Secton: [7YC ROuGwup:; f LROGroup iJ vilt-volui T [EngineeredSafety Features Actuation System _ 013
- ta~t~intl iKnowledge of bus power supplies to the following:
ESFAS/safeguards equipment control 6 1i Slwill automatically actuate. both trains. Train B ESF Loads however have lost the relay (energize to actuate) and will not auto start as designed. They can be manually started. (A) Correct (8) incorrect - SI will actuate. Train B will not auto start (C) Train B will not RO- -li-ti TR.....W jfi*; - . l;A w.....
^
,_ _ __ _._ _ _ _ __j _ __ _
Ssb sof3 1gBO0_ EL ECl
,Losso nstrument Bus _ [BwOAELEC-2 _- table D Ji18 J
__ _________- ____-=~ i_ ----- ~ ---- ~ -_ _J=
J_ -~
~Rq~do~akalgJI-____
Ralrletl Roquled MW Examinato j= _.__ _ , ______ _ ___.____ _
PWIl in ] Facility Exam Bank J 9esltllo Modfiatilon Method: fEditorially Modified Used Durhn tm dng Program Mn oure §Rmet r---- ------ . --- :T -- r______ _uevsoy
- r------ ----- - -- - ----- ____------------~-- '---- -...............
--- ] I
- Fac~lifty NRC; (6;
Question Topic ergineered Sa'ety Features Actuation Systemn IESFAS)
Concerning the Engineered Safey Features Actuation Svstem (ESFAS) there are (1)_ _ channels of uirrow ratlh-e steam qenerator level instrumentation on each steam generator .vhich input to (2) independent safety trains of ESF (1) (2)
- a. 2 4 b.! 2 2 C.. 4 2
- d. !4 4 Ii Anwr xmLvl BjCgiieLeve JFemory_____j Facilltiyj [Braidwood- _jxm ae 7/19/021
~KAj 1013000K501 K5.01 RO alue: 281 iSRO Value: I F 2 JS~.c j FSYS RO Group: Li RO Group:~ j SvisemIavolittlo-nTMI-1 FEngineere SafetyFaue Actuation System _________0113 4(A-l~len~nL Knowledge of the operational implications of the following concepts as they apply to the Engineered Safety Features Actuation System: ____
Definitions of safety train and ESF channel eeae2independent trains of ESF (A&B). Each train will receive an input from each one of 4 level channels on each steam f
~Fggenerator for ESF purposes. (TS 3.3.2) (C) is only correct combination Reroco ltip- alilt~eficeNumerlJ C _ill~- I Pge No.F ISecion IESF LP -____EF-XLI 01 -' F~ 5,7 1
[Tech Specs ICO__~~~~7 13 -I aladrial Re idrd ftr Examination__________
_N__ §jl rlModlflcat o ehod:
l - Us d Durl _
~ommmt~& CommntaI 717__
~777I~i77~7 SUpervlsoryll
____Facil11ty NRC:
Question Topic Rod Position Indication System (RPISl The following conditions exist on Unit 1
- Reactor power's holding steady at 1x10e-8 amps during a normal reactor startup
- Individual and group position indicators show all control bank D rods at 120 steps withdrawn When the NSO beglns to withdraw control rods to raise reactor power, the IR NIS indication Sudclenly drors tby 1 .3 decile and continUeS to decrease at a negative (-) 25 DPM There is no significant change in RCS Tave The control bank D step c.:tnters no.% ead 121 steps for both DI and D2 groups DRPI indicators for rods D-12. MI-4. and H-8 indicate 0 steps All other rod postio, indicators iDRPl) are unchainqed Which of the foIlow-ing has occurred based on these indications'?
- a. The control tank step counters and associated DRPI indicators along with the NIS indicatlons are consistent witn multiple dropped rods
- b. The Individual rod position indicators appear to have failed. more than a single dropped rod would ha-e resulted in a reactor trip C. The control bank D group 2 step counter has failed, it should also read 0 steps if the rods in this groiup are fully inserted
- d. Either the control bank D group step counter or 3 DRPI indicators have failed. not enough information is provided to determine which lLnr ivf Lev - igf=
Aptcation Faciltyj Braidwood ExamDate: 7/19/02 fK:AI [014000K102 ] K1.02 [ROdValue:F 'SROV Wil F 3.3 `Sstlfn SS I rRffGroup:i 21 f¢SROGrou:f 7rJ Systr/Evodutlon TaIb Rod Position indication System _ 014
-SbbM-ffft] Knowfedge of the physical connections and/or cause-effect relationships between Rod Posibon Indication System and the following:-
NIS l dia pf Indications r provided are consistent with multiple dropped rods. (A) is correct. (B) incorrect - the reactor does not trip from neg rate l 4 (C) incorrect - group counters are demand indicators only. (D) incorrect - given NIS response. DRPI or group demand counters have _J S
.. ;JS MflCJ St OIC_;
%CSa. tS W SJw;
.Abnormal Ops - Dropped or Misaligned RodJ1BwOAROD-3 lSymptoms s f _1 Bwd Big Notes JtRD-6 - - jl_ _
______ _ _____ _ _F6 . ndc_t-ns 2 pMBW equiired for Examinatio i'I
. I
~i~~7j Exam Bank 1~9usoton Modilication Mettiod: Editonially Modifie j DungrangPorm
_u~iccmsw
-46u ~ O'Llesim
_ainnil r.
-- - -- _ -- Superviiory; Facility NRC'
-11
Question Topic N(.clear lirstvmeruntatron System Which of ttre followingq describes tne effects of a short un-ntentlornal emnergency boration on the reactor al 75 -' po %er Ass.rne that control rods are in MANUAL
- a. Tave initially decreases causing reactor power to decrease Tave then increases to approximately the initial value
- b. Tave initially increases Calsing reactrI power to decrease ave then decreases to approximately the intital value
- c. Reactor power initially decreases causLing Tave to decrease Reactor power then increases to approximately the initial value I d. ! Reactor power initially decreases causing Tave to increase Reactor power then increases to approximately the initial value t
7/1 9/02_.
lc ;Exm LevelI B CogniWt Level Application FacII-lBraidwood _J mExamat 7902 y-vof
]i t
7 nibJ A1500OA107 A1 07 I'OVal _ Secihn l SYS RO Group: 13 SRO Group: KJ Instrumenta-tion System ----- -[Nuclear
= -- 015
- Ability to predict and/or monitor changes in parameters associated with operating the Nudear Instrumentation System controls including:
Changes in boron concentration 1f Boratbon is an added poison. fewer neutrons available for absorpton in the fuei. reactor power decreases. The decrease in reactor power results in a lower Tave. As Tave decreases. (+) reactivity is added causing reactor power to increase. (C) correct respoonse.
- RebrencI- J[
Normal Operating Procedures
-- - - [ i "ac i
- Reference Number] I jwPCV-6 jrecautons - F14 I 1 _ _
F7 ---
==----=-------
-----__7_-
I I _
I rbRequiredfr ExaminatUon jl=
K_ ___ _ _______J__
___J __
____ Facility Exam Bankk" o e D F Source Puon SourceCommients !
lornment Type Commnent - i _ -_ _
IRevews Complete
-- - - - -. j F 77-j ______ ------- 7- ------------- 7---- -- 77--
I I
7 -----
7------ 7---- *7 *77 77 ___
,_, I
- - - 7 77- 777 -- --
I Faclthy INRC'
-a~
Question Topic Nuclea! Instrumerit.otOn Syser'i The following conditions exist on Unit 2
- A normal reactor startup is in progress
- Reactor power is steady at 1000 cps
- PR NI channel N-41 has failed low
- Operators have completed performing 2BwOA INST- 1 -Ntsclear Instr Jinentation Malfunction- for the fa:dŽd PR (i -...
el Seconds later the control power fuses Dn PR cn-i"el N-43 both indicate blown Which of the following describes the next action !o take
- a. Verify all rod at bottom lights LIT
- b. Manuatly reinsert all control bank rods
-c. Manually reinsert all cooitrol 3nd shutdo.wrn banks
- d. Complete the starlup to <P-10 using only IR instruments
- Level! [B o _ _evl icaic _ i! _ _
0 RCognitivale: Facly FBraidwood - ExamDate: jl71902:
kA [ 6 1500OK604 RValue ] F31t SRO Value j 2 bction SYS fRO 0SROGroup:;
Group:
l jj lSystem[Evoltioi~ TW (Nuclear Instrumentation System _ _ _ 015
[Knowledge of the effect of a toss or matfunction on the following will have on the Nudear Instrumentation System:
Bistables and logic circuits 1autornatic trip on PR instruments is active. even at < indictaed PR power. SR instruments are de-energized due to P-10 pickup (A) is correct. Candidates may confuse 2 PR channel failures with P-10 actuation and blocking of SR instruments which make J
_ .. U O. I. .A _.j .t ... t
_____ TteFachftyRefer~neteNumbew.
_ici ~!Ain -~a N.N - -ieri IBraidwooBig Notes j1 -2 j[ r---
Material Requred for ExwMniatlon -- _ ---
Sore New Question Modiflcatlon Method _____ Jsd During Trahthgkmr Aetion So rce C mfnta]
IComment Type ICmmn jib --- ~-IL44"es Complefte
- . J- ~ k ~ - --- - -- - - __ _ _ _
77>716U G~Sp~ory IFacility NIRC
Question Topic Non-Ni,-iear Instrumentation S~stem iNN'S, Which of the follo.-,ing Ma~n Control Board recorders provides the operator with the option of SELECTING specific caimels for trending?'
- b. 1PR.937 Containment Pressure C. 1PR-0514 Steam Generator Pressure--
d.: 1FR-051 0 Steam Generator Steam Flow/FeedFlow
___EaIvCJB ICgltvL.lfMemory________- 'Fcit 1 ridwood -- ExamDate: /19/02 7___
~Wi~6OOOA402 IA4.02 R Va e: O iu j f~ Saction: fSYS ROGroup Grout. I OrjatIiEvokiution TIJ Nn-Nuclear Instrumentation System___ __ ______ 06 VA Saiaintt I Ability to manually operate and/or monitor in the contro room:
Upf] (A.B,.D) have no capability to sectotna channels on the MCB. (C) has 2 channels available with a MCB selector sic n -
~~7R~~~1PM0J. -1_ _] Ntibr
-Facflty opr Nubrj n~i~Sc 1N[ii [R !4-
.SGWLCL~P IiVi _11--W-XL-01 14 jj§aI Required for Examiato- __ _________
New 5~Mdifl.Uc~Me~ld:7 _ __ J ~D uting Trahilo Program
,WCon rnt Type- Comment& -___ ____ _ __ ____ ____ __
___ ____Supervisory
--- - Facility
!NRC
I uestion Topic rI-Core TemperatUre Monitor (ITM,`I Systemn--.
The In-Core Temperature Movitoring Systemn is utilized as part of the Power Distri bution Monitoring Systen (PD'.S iAs such, the MINIMUM TLnumber
. of Incore Thefrmo1COUples required to be OPERABLE is (1) with greater than or equal to (2) detectorls per core quadrant (1) (21
- a. 11 1
- b. 14 2 c.. 17 2
- d. '203 li ["vM n__Cognitive E~~Level R- ontv Levelj
[ i]
atMeJj~coY [Braewood jExamDate: 71901 KkA] 070G222 d2.2.22 ROVlu: 3.41 4.11 $SeCtlon SYS OGim:I 1op Aystiiyl~l*utlon 'Vtile~ [1n-Core Temperature Monitor System________ __0 17 Frnowte-i;ge oftlimiling conditions for operations and safety limits TRM 3.3.h requires 17 with greater than or equat to 2 per quadrant. (C) Correct ITeh ReuiemntMMnulPDMS 3.3h !h-5 J 6 ___
"ateiril W"ul. for Examination bui*InAfaft mii tj I ..- - 1 Lr-n.~~~-. 1Irw j mimiinuuuuuumn uMmmoaIM:.. I j Used During Training Program
~Iomnt~y~ie -- -ent----.--- CLwoimplte
__ - ,P i yII
-is
Question Topic In-(.re Temperature Monitor hITNI) System A Loss of Coolant Accident has occurred. core exit thermocouple ICETC) ternperfn ures are reading 690 F and increasing Which of the following describes the expected response of tt-e CETCs as the Reac¢tor Cuolant System and core exit tenmperatures continU¢ to increase (Assurne no core cooling is present)
The CETC's vill indicate
- a. tower tMiarn actual temperature above 700 F and will stop indicating altogetner as temperatures exceed 1200 F
- b. accurately up to 1800-F. a-d can be used for trending purposes up to 23C0 F
- c. higher than actual temperature above 700 F. and cannot be relied upon for accurate indication above 1200 F
- d. accurately up to 1200'F. and wilt fail completely above 1800°F
?Anslwe] [!3 JExam LevelIR JCognitive Level I FAppcation I Facility:]FBraidwood ExamDate [ 7/19;02; 0_7 _ __le ~tcr-- r RO Group: 1 SROGrOUp: - -S j1 KA:I I!700K102 K1.02 vROValue: _ # OVa hectoS: _
yften volution Titj In-Core Temperature Monitor System l 017
!State nt I Knowledge of the physical connections and/or cause-effect relationships between In-Core Temperature Monitor System and the foowing:_
RCS ten O l CETCs usable range is 200-1800-F. They are expected to indicate up to 2300F with reduced accuracy. (B) is correct .
f Reference Tlide Ytl' __ ___
1rne~c~~e _
N]
Cvsifl
.. Nu er-Inadequate Core Cooling System LP 11iIT-XL-01_____ _ 8 l_ ____is ____
_____ __ __ _ _ _ ___ ___ __<___ __
- __j _Js I
______ _ . _f__ __E____
~IWeIalRequiredforExamnanUon __ __ __ __ J Facility Exam_ Queston M1et1od: Significantly Modified Uased During Training Program
__t"Uii SeCommenig j
_eer, _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Lom nTypi jomnt ui~~ ~omeM ________________Reviews Rvopb Complete r- rSupervisory -
j__ rFacility NRC
RO SkyScrerr SRO Skvscrawer I RO ltsmlEvoitionList ISRO SnbeitVEvolution List Outline Chanes I .'
Question Topic Containment Cooling System ,CCS)
The following conditions exist on Unit 2
- The reactor is at 100% power. steady state
- 2A and 2C RCFCs are running in high speed
- 26 and 2D RCFCs are in standby
- A reactor trip and Safety Injection occur due to a large t'eaik RCS LOC(A Whicn of the following describes the low speed stan response of the RCFCs after the SI signal s received?
___ _ _. _ _ __ _ __ _.__ __ _ ____ _ _ __ ,~ p ic ~ n Faiit_ _ _o Answer1 aj m BJ*: lApplication I L*VellBraidwood _J F tj ExamDate: 7/19/02i 1022000A401 A4.01 WValuuej [ J SROValue- 3 : SYS I RO Groupj J SRO Group: 7jj SystlienEVo dlon Ti FContainment Cooling System = = 022 MStaboo~t lAbilityto manually operate and/or monitor in the control room:
ICCS fans I~iii~~i Fans already running in slow speed will remain running - none are in this example. All high speed breakers trip (2A 8 2C). After a 20 second bme delay. slow speed breakers close on non-running fans. (A) correct response.
!; 7 -R~rinc. _illFacility Reflernce NSbe _ n cion 9. No.
v,L.O.Nunb Bwd Big Notes _ Containment Cooling l_ 5 J _
___ ____ I, _ __ __ __ _______ ~ __Y __ __J __ _
______ _____ =__ _ii~7if. __ __
IN Facility Exam Bank PuesUon Modillcalon Mtho Significantly Modified l Umd DurngTrainingProgramr I l
.-- . ~7kXh7II I1 bws Complke _
lPeer -- - 1-Ii - - 7 . 7 Zi .. 7-I.......iII-i-1 I!- ... - - . -i supervsory
'Facility I NRC 11
Question Topic Containment Coolinig System (CCSi rte following conditions exist on Unit 1
- A small RCS LOCA has occurred
- The crew is performing 1BwOA PRI-1 Excessive Primary Plant Leakage'
- Containment pressure is 2 9 psig and increasing slowly
- RCFC 1C low speed breaker auto SI closure relay failed and was declared inoperaple
- Annunciator 1-3-E5 -RCFC LOCAL CONT-, is LIT
- RCFC 1C is in LOCAL control at the RSDP and running in HIGH SPEED Which of the following describes the available operation of the 1( RCFC in the curreret configuration if containment presslire continues to rise to 4 0 psig?'
- a. The high speed breaker will automatically trip the low speed breaker CAN ONLY be closed from the RSDP 20 seconds later
- b. The high speed breaker w.ill NOT automatically trip the !ow speed breaker CAN NOT be closed at either the RSDP or 1PM106J
- c. Tne high speed breaker will automatically trip the low speed breaker CAN BE manually closed from 1PM06J 20 seconds later
- d. The high speed breaker will NOT automatically trip, the low speed breaker MUST BE closed locally after the high speed breaker is tripped A w orlI jnsExam Lvel i Cognitive Levl jA pication lt raidwood9/02 Facilt Exa mDa
!K: 022000G43- . 2,4,31 W Value: 1r3i31SROVfu: l 34 Soction:l rSYSi ROGroup:jl71 SRO Group:] [71 Tlo_] Containment
__y__-Ewiutbn Cooling System _ 022 KA __ se _ __t__
Knowledge of annunciators alarms and indications, and use of the response instructions.
iAL CONT indicates that the high speed breaker for the RCFC is in local control. Low speed breaker operation is unaffected by the Local/remote switch. (C) is correct (A) Incorrect - low speed operation is not available at the RSDP. (B) trip,1PM06J l low speed operabon is available.
Reference Tt i Facility Reference Numnber ci on 1
a FAnnunciator Response procedures ; 1NOTE _BwAIR J i13-
--- f I-------___-_ _ _ NOTE j Matweia Reuired for Exmnination _ __ --
nSource1 New -- M Ifloul-- t Ued Durling Training Prograrn ll-on Sourc Comm ent IA H~ommient Typ Cmn~nii -__- --- ~ - ----- [ RvX~ornot.e t pow:
.J. Supervisory i;Facility NRC 78s
RO SkvScraprl SOSiyscraer RO %stsgnlEvolution Lst I SROSvstewaEvolution Lst I OutlinaChanoes Question Topic Containmenl Spray System (CSS)
Which of the following valves is interlocked with OPENIG of the 1A CS Pump Suimp Suction Isolation 0 alve, 1CS009A'
- a. 1SI8809A RHR Cold Leg Injection Isolation ValIe
- b. 1SI8811A 1AContainment Sump Isolation Val.e
- c. i 1CS007A 1A CS Pump Discharge Isolation Val.e d.j 1CS001A lACS Pump RWST Suction Isolation Valve -
jgg _* _ _'_ _ __ __ L _ .r__ _ _ _aooc .Exa. [ _at F 1026000K101 K1.01 21SROV f a I S RO Group:i [ J R°OGroup: 01J
$ysbelp voluv feuMit le I ContainmentSpraySystem ______ ____026 I___
3 l Knowledge of the physical connections and/or cause-effect relationships between Containment Spray System and the following: J ECCS qt Interlocks for opening 1CS009A are- 1S1881 1A Open, 1RH8701A Closed. CS to Open. (B) is only correct answer. (A.C.D) valves n: are not in interock circuitry and are incorrect ..
-Reference Tide -- sc1tiy
- Refernme Nbe eo. ivlon] o. Nmer]
_ __ .__ .__- _---.-- -ii - -- -Pw --- Ls-oii-N-- _
{CS LP 11-XL-CS-01 J1l j!1116 1 IS-CS 1-08.A Bi Note _r ray ____ I___
BwdBigNotes - ContainmentSpray _lCS-1_ _ i 15 _
I_ - _ _I_______ [IZ~__ __!- Z7 -- __* I7 lI~ .__---- E__
"t&"edpi*edfwtrExarrntfon j -- _ - -_ -- ---- -
tb8 ui railt Exam Bank Qusto _oic
_bn~d- [Editonally Modified dun§hga r _ c--e-.l---
y1 _ ___ _. _ _ __ _ n _ _
r_ _ _~mn~
FommentTy-- - - RevbmCom pbei
_1 _~ ___ _er _
r.-- - Jl_ - - - Supervisr F-- _ FaciIty
._ I NRC
Question Topic (.onta.nnient Spray System ICCS)
The following conditions exist on Unit 1
- A reactor trip and safety injection have occurred due to a large break RCS LOCA
- All ECCS equipment functioned normally upon receipt of the SI signal
- Five (5) minutes after the SI was rece ved. Containment Spray (CS) actuation setpoint was exceeded
- Train B of CS started as designed
- Train A of CS did NOT auto start anz could NOT be manually started from the Control Room Which of the following anrnLncators, if received JUST PRIOR to reaching the CS actuation setpoint. would result in the above status for CS?
- a. 1-21-A4 BUS 133X'133Y FD BRKR TRIP
- b. 1-22-A4 BUS 134X 134Y FD BRKR TRIP
- c. 1-21-AlO BUS 131X FD BRKR TRIP
- d. 1-22-AlO BUS 132X FD BRKR TRIP u~rrj c l7Exa v r C[nfntiveLevel [Appicaton j 1 Facilhty: Braidwood _ ExamDaft: 7 77 9/02 nKAiJ 026000K202 K2.02 RO Value: 27 SROV64atu. F29 nc.on: FSYs RO 2rou SRGrp rl2 Fo_260OOKi ___ 9:-I Group:RO Grup:.,
jStmnVEvoIutionTi Me Containment Spray System j026 sta e z Knowledge of bus power supplies to the following:
__________________________________________________I MOVs l Inteocks -to auto start ICS019 must auto open. Power supply is 131X1. For CS to be manually started. 1CS007A must be dosed.
.. Power supplyis 131X5. To start in recirc, 1SI8811A must be open but we are not in recirc yet. (C) is only correct answer. (D) iAt V - UOa.. IS .D.- rflALJ JV* - -tII... 0*, 1-. 0 3U
. Q-*cvO.
7~-jY4W"ifi~ e-ij__ ~ -----
__ I ________ S9cn]0 iageN7 4IIO~O~mef CS essn Plan I ll-XL-CS-01 - ~ ___ 12 -15___] GS 1-1 6 BwdBi NoesContainment Spray CSJ~-- 15-l attrial Required for Examination stoo Sore e usio oiiainiedo~_ _ _ _ ]sd~dgullgrga I
r~e, 771 - -- _ __i-Facility
Question Topic Hydrogen Recombiner and Purge Control System (HRPS)
Under normal plant conditions, opening the Post LOCA Hydrogen Monitoring oiwtsde suction and discharge isloation valves 1PS228A B -
1PS230A B. is accomplished in the Main Control Room from (1) and indication of containment hydrogen concentration w 1inormally be displayed on the (2) scale
- (1) 121
- a. 1PM1 1JI Unit 1 Containment Isolation Panel HI
- b. OPM02J Unit Common Ventillation Panel LO
- c. OPM02J Unit Common Ventillation Panel HI
- d. 1PM1 1J Unit 1 Containment Isolation Panel LO Atnw [ -- Exam L [velIfB l Cognitive Level [Memory J_lFacity Braidwood ExamDate: 7-l9/021l KA.j l02800;0A403 A4.03 ROVai:j l32 SROvltue:i rI; S33 o I F SYS IROGdroup: I 9 SROGroup: 1 SysEvowlon Title Hydrogen Reombiner and Purge Control System _ 028 IKAdihty to manually operate and/or monitor in the control room:__
Locabon and operation of hydrogen sampling and analysis of containment atmosphere. induding alarms and indications Ex~ti 1(D) Correct - Controls and indicabons for 1PS228. 229, and 230A&B valves are all located on the Containment Isolation Panet.
1PM1iJ PS343 and PS344 are normally selected to indicate on the LO range (B&C) incorrect - controls are not located on L! Fa lly, Ref.eeieice N!! b~rj Ssction N No.]j[.VIoJA'wb]
I Normal Operating Procdures; FoPS-9 Bw--P ____ 2
[~i ] 78IE2 I MaIs equired for Examination _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
___ ___Question Modilicallion Method: I __ j5edDuring Tra Pngimn Oumuon iour, nwenia
- I.-
ommentTyp.j on1ment - -- --- -- __-
.[RoyIwsc offpbb.
K3j 7li7 - ---- _ _ ___
7 - ---7-i7 - __ __ __ Supwvlsory F' -- -- Ii .11-F-I- 77 177---
Facility NRC St
RO SkvScraper SRO Sknur l R R0 stvEvotion LUst SRO SysbtnIEvolttiogt List Outline Changes Question Topic Containment Purge System (CPS)
~L-7i The following conditions exist on Unit 1
- Reactor is at 100%, steady state power
- Containment purge is in progress and is being performed under BwRP 6110-13T1.
-Containment Release Form
- During the release. Health Physics requested 1RE-PR001 be placed in purge for a filter change Which of the following actions must be taken pnor to placing 1RE-PRO01 in purge to comply with the requirements of BwRP 6110-13T1 and RETS 2 2-la9
- a. Suspend tfie containment release of radioac- ve effluents via this pathway
- b. Obtain continuous samples of this pathway vith auxiliary sampling equipment
- c. Restore the monitor to operable status before the next 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> sample is required Id.j Verify that Cnmt rad monitor 1RE-AR01 1 is operable and continue the release I, L lar VeIeveljCo Co[m mprehension l iiW F _Braidwo - Eamvat-eY1 =_ 7/19/02 I F02900A204 A2.04 ZROVah_[J r 4RdOVWe 123 0 FSYS I R Group: l_SROGrouwj [7 fiysbiieEvoliaiii*ti. Continment Purge System I 029 staitemen Ability to (a) predict the impacts of the following on the Containment Purge System and (b) based on those predictions, use procedures to correct. control. or mitigate the consequences of those abnormal operation 111va'ul ii 'yzWC.5 bdirnl~ing ox conwainment atimosonere I __ L. B __ __ I isolabing 1RE-PRO01 renders the noble gas activity monitor inoperable. RETS 2.2.la requires immediate suspension of purging via I
_this pathway if this occurs. (A) Correct. (B) incorrect - this is an allowable option only for the iodine and particulates functions of
- 1_-.
- . U. C., @U* CO O... *C-4 U.-V-.
.-..Pt..* **- Ct.t - ;au. r. *,,aQs.;;
J CJ.-L-t l
feren Tilts wTONumb ___ ~ FltC11-Y Reftrince N ,Sbn t ] Pageg Noj]
id r]
ODCM RETS - Gaseous effluent monitorn lRETS 2.2-lga r 8120 f V -
_Rlease Form BRP 61 113T1 7 11 IF_ __.]_ i 7 i
~uis~lRequk"dtrEa~io.j -_____J
_u Ma- Fodbu _-_
nS lNew j lodlonLen -d . r Di Trainin Progrw
~ton Sourceommnh1 l similartorecentBwd LERevent
,Reviws Compblte ii FILL ---.-.. -. _____ __
.1 1 Supervisory I- - -- ---
.---.--- -- FacilityI NRC
Question Topic Coritalnment Purge System (CPS)
The following conditions exist on nit 1
- Operators are currently performing steps in Post LOCA Cooldown and Depressurization tBwEP ES-1 2
- Containment Mini-Flow Purge Exhaust and Post LOCA Purge Exhaust fans are aligned and running Which common mode faiure will result in BOTH the Mini-Flow Purge Exhaust Fan AND the Post LOCA Purge E xhaust Fan tripping> 9
- a. Closure of 1VO0C5A, Min Flow Purge Exhaust Ins'de Cnnmt Isolation Valve
- b. Closure of 1VO005B. Mini Flow Purge Exhaust Outside Cnmt Isolation Valve
- c. Manual actuation of deluge in the Post LOCA PUrq;e Filter Unit
- d. High alarm on the Cnmt Purge rad monitor. 1RE-PRO01 Answer a j LExam Level R J :ognlve Level I Applicabon J aFacility: FBradwood ExamDato:JF O 7T19/03 029000G449 1A:I W2e449 I r40 4ROValue: ISROVab . i 4J Sectlon:J SYS O Grotap:i i2 SRO Group: __2 lpyatimlyvolutllon Titleb Containment Purge System = = _ j 029 Ability to perform without reference to procedures those actions that require immediate operation of system components and
[controls.
n (A) Correct - VQOO5A is interlocked with BOTH the mini-flow purge exhaust fan and the post LOCA purge exhaust fan. (B)
. -21I.-Incorrect - VQOOSB interlocked with ONLY the mini-flow purge exhaust fan, (C) Incorrect - this action will auto dose V0003 which Ir
- 0sana o.,,uU u.
0.ou~ unVS OL
.41 ... , .. eyVi~ C .al
^oa ..... 05 tlS,
... 0Y.
- vr ni, Iv %.
- lesw -tiSSVI,-. 5 a. *SSSSS50 o0 ~ ~~JSat owovouuv
-l>ewl@v tLOUSS
___- . Rtenb - .-- - V-2FdtReftrni
-~ ---- ------- Nmb r RetofC1P~ _ ____ p~ O. Numb ir I.
[Bwd Big Big_ o Notes -Cnmt
,e_Purge -IP- ___ ___
_ _ _ _-- - - _-.-_ X 5
!--_-I
,__ _ _ _ _ _ ___ _ _7 _ __ _ -I__ - .-------
I Rai~dfRe d for ExanllnaltlonJ_ _ __j
$s~notwcel: Ne - lnoliainto:_ _ ~_ ~dDuring Training Program
~ - 1 Rvlewcomnplete
~-~ ~ z~c~::f~--:-~
71 7<---
-- - pSupervIsor 7 - - ~Facility NRC
Question Topic Spent Fuel Pool Cooling System (SFPCSt If a lea., develops on) the discharge of the Spent Fuel Pool Heat E xchanger while the cooling loop is in operatior the Srent Fuel Pool voll lose a MAX IkUM of ill before the FC Pump loses suction Jsing BwOP FC-1 1, makeup water will be a~clecl back 'o the Spent Fuel Pool via the 121 (2)
- a. 41feet Refueling Water Storage Tank (RWST)
- b. 4 inches volume Control Tank VCT)-
- c. tinches Refujeling Water Storage Tank (RWVST)
- d. 43feet Volume Control Tank (VCT) nse a Eam eel -- Cognitive Levelam6ate:w-j AnweevEamLee J[plication JFcxit:mF~aiwod 7-19/021 sea . F0O300A203 I A2.03 ROVlue: F3j] -sR--value: 9-35 Fseciition: 4SYS RO-roup: {R ru1r 32j SysternlEvoiutlon Title !Spent uel olCoinSystem _______ _ - ]033
____a ftei Ability to (a) predict the impacts of the following on the Spent Fuel Pool Cooling System and (b) based on those predictions, use procedures to correct, control. or mitigate the consequences of those abnormal operation:
I(A)
Abnormal spent fuel pool water level or loss of water level
~*ianai~~ Correct - the pump suction has stops 4 feet below normal water level. The RWST is an available source of makeup water. (B)
~B~er:4~jIncorrect - the 4 inches relates to the anti-siphon hole on the SIFP cooling discharge to the pool. The VCT also is not an available Incorrect- the VCT is not an available source of makeup water.
__ ~
Rfeec ~le-- f Facillity Reference Number efrnce Section Page No.' RevIsIon L.O. Number rSpent FuelPool Level Adustment Proc FBwOP FC-1 1 -- - - - : .~3 20~ 9 S~pent FuellPooicoohng Lesson Plan - Fl1-F-XL-0 1 j ____5-- ]1 jS6 Materiial R equir d f~or E xam ~natio _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- _ _ _
Questlion Sourcej Ne Question ModiflIcation ,uuwd _ I_Used During Trainng Prora Question Source Comments Comment Type I 60M--M 0r1t -Revle;40omplete
-=--
f- --- __ _ _ - - --
- - - **: - Iuplervioryl
- Facility NRC
Ouestion Topic Fuel Handling Equipment System (SHES, What prevents raising an irradiated fuel assembly out of the Spent Fuel Pool using the new fuel elevator?
- a. Controls for the new fuel ele.ator will only travel in one direction
- there is no upward motion available
- b. Upward motion of the new fuel elevatcr is stopped f surface radiation levels approach 100 mr/hr
- c. An upward motion interlock prevents lifting any loads greater than 1200 lbs with the new fuel elevator 1
- d. A slack cable interlock prevents raising the much lighter spent fuel assembly via the new fuel elevator Anwe _______ [ei lr orfJ l~~ [Mmory JaCUiity:J vE
- _ _ I__ _ _
/1 -
K^A: F034000A302 Mffei~voluti~on itl A3.02 -RdVale 1] 2 5 1 SRO VS f Fii i tfi R jSY-S il 3u
_RO F 2o1 Fuel Aandlih Equipet Syste WI - -- --
ILK KA8tuteww~ Abili to mperatios oftheFuelHandlingEquipmentSystemincluding:
Load lmts-euwr oo nelc st (C) Corect the padmto nelc st prevent raising spent fuel out of the SFP, maintaining over the SF for shielding concems. (A) Incorrect - the new the required depth o ae uef elevator does travel upward (B) Incorrect -there is no rad interlock
- 'i
] f acl_ yL ierene.E---J FIuel Handling L _ - _ j IV FH-XL°01 _______ 1 r-beI
[Rcton_[zieo 1 6 0W tr
[---1 ----- 7i[Iii
-L-P__ O __ -- 7j_
L~L ~ ~~ ~~--- ~ 1 _ I_ ]
R~t~ j J . ___ -
-_-atnj- ---- ~I-- Ets~eqs= _
rJ --
Qu tion ou eCo mn 12001 Praine Island NRC j
Ir-T--
=-=- --.------ . ]1I I - --
r-=:--- - :7r---- -- ------- ~ - ~-- -= ~ p _
-_ -- -=-___ -- _ _ S p toy rFacl]t NRC,
Question Topic Fuel HandlirCg Equipment System (FHES)
Unit 1 is in Mode 6 and his comr'enced core off-load The following conditions exist
- 1B EDG is OO for overhaul
-A 1 FHB Exhaust Filter Plenum is aligned and in service
- Containment mini-purge system is in service
- Fuel Handling Building Radiation Monitor. ORE-AR055 is OOS
- Fuel Handling Building Radiation Monitor ORE-AR056 alarm circuitry has lus! failed IMD is troubleshooting Which of the following describes the required ACTION. if any. to be taken in order to allow core off-load to conlinU&e
- a. No ACTION is required, fuel movements may continue uninterrupted
- b. Core off-load can NOT be conducted until at least one of the FHB rad monitors is repaired
- c. Fuel movement may continue for up to 7 days while restonng one (1) FHB rad monitor to operable status provided 1B FHB Plenum is aligned in the Emergency Operating Mode Exhaust Filter
- d.' Fuel movement may be conducted indefinitely provided __ __ . ._ __ _
an appropriate portable monitor is provided and the 1A
- aligned in the Emergency Operating Mode FHB Exhaust Filter Plenum is LFrwerj [-j IB Cogn LAppcation - F-_l t EX r 7/19 0211 F_602 K6 02 uRo e] [6ro IU E ov3 H 3 In - SY RO Group: _ 3 RO Group:i 2I y vEvohftn inftl Fjuel Handling Equipment System 034 En, lKnowledge of the effect of a loss or malfunction on the followingwillhaveon theFuelHandlingEquipment System:
Radiationmonitoring systems
)inrrect- pe TRM 330 wio FHB Vent in emergency mode and provide portable
- .1 fuel movements.(B) Incorrect - may move fuel monitor or stop with vent alignment and protable monitor (C) Incorrect
- needto also place portable account.
_~l _~
2dadling LP .c _
Ffeh FLj Requirements Mna j X -1 1FH-XL-011 7ii1 __ __
232 26-32 .52 J7.1 0
_RM 3 3.o0 --- - ---
. 2 -, 5 - - =-
=_ -- r=-----=i-_- _ -
_~~~~
=-___J1_ - - = - ----.--
-.- J
____,_j I W Re~red for E II ni_ o
- q * . e -f =
J New ____ _
- l j
tmkuI __ __ _ _
____JI_ ____-____-_____-_______-_
-- 7
, -- r---
- ------------ ----- __ _- _- _-__ __ = .rfsr
_. Facility NRC
RO SkyScraper l SRO Skcrr RO SYSt"lEvoE on List I SROSYS1011f11EWl List I OutlE ine n es -al Question Topic Main and Reheat Steam System i NIRSS; Prior to start up following completion of A2R09, the Unit 2 Mla ri Steam Isolation Valves (MSIVs) were tested to enasirea closure lime and that each MSIV actuated to its isolation positior on an of < 5 seconds a.: ujal or simru a-ed actuation signal The basis fc p limit or mitigate all of the following EXCEPT iforbmng these surveillances was to
- a. Accidents that could result in offsitle exposures compa'able to 10CFR100 limits
- b. The potential for uncontrolled RCS cooldown arnd pos ive reactivity restart accident
- c. Total mass and energy release into containment on a HELB
[d~]k~nLv- Ll mprehensi dwoo S ;-i9 Lvsl Brai___ ExMJ 2 7/119/02!
t O39000G225 2.225 Main and Reheat iV lue:
Steam System 25 [ROVaiue.: J 37 S j u SYS ROGroup. i2 SROroau.] rF2 j39 10 KASWei*a KXnowlendge of bases in technical specificabons for limiting conditions f i for operations and safety limits l(AB.C) Incorrect - these are not exceptions - they are basis statements for MSIV operability (D) Correct - Credit
. 1 MSIV operability b protect against turbine overspeed. is not taken for ii f X - .F a&Fify Rfcillit m jfteersnN Sec _ NUon3 FIiUr.A Tech Spec Basis - MSIVs J _37 j2sis f1 7 --- Fr----
_ _ _ _ __-_ __ , F- _ _ _ _ _ _1
___ II
§ jb j] New _ j I sffan Mi1fOSO ., __ _ _ ~Jsd fDuring lriioga I___
I __ -----
Iomn _
_ _p
_--- 1
_ ------_.J - -AM - -_
ft_
S Fcll
'NRC 81i
Question Topic Main Turbine Generator Mll- G) System The following conditions exist on Unit 1
- Reactor power s 80%/. steady state
- All systems are in automatic control
- One Main Steam Dump valve. 1MIS004A fails 100 i6 open due to a valve positioner failure What is the expected response of the plant due to the steam dump valve failure AND what action can the operator the excess steam flow' tak1e from the control room to stop
- a. Turbine load will decrease by approx 3 . AND reactor power wilt remain constant The operator can stop dumping either Bypass Interlock Switch to OFF RESET excess steam by taking
- b. Turbine load wi remain relatively constant AND reactor power witl increase by approx 3% The operator can taking the Steam Dunip Mode Selector S: ttch tc STEAM stop dumping excess steam by I PRESSURE
- c. Turbine load will decrease by approx 3 -, AND reactor power wilt remain constant The operator can stop dumping the Steam Dump Mode Selector Switch to STEAM PRESSURE excess steam by taking
- d. Turbine toad will remain relatively constant AND reacor 3 power wil increase by approx %/x The operator can stoo dumping excess steam by i taking either Bypass Interlock Switch to OFF/RESET
[nj ixamelelJ [B Cognitiv Apptication _ Fdcity:! Braidwood ExamiDate, ____ 7/1/2 KA: 045000A208 J A2.08 AOVle: r6v-h1
- 1 131. l n l
lR.iGroup:j FiSYS 3. 060topi
_______________ Main Turbine Generator System = =_l 045
_KAStatement Ability to (a) predict the impacts of the following on the Main Turbine Generator System and (b) based on those procedures to correct, control, or mitigate the consequences predictions. use of those abnormal operation:
Steam dumps are not cycling properly at low load, or stick open at highertoad (isolate and use atmospheric reliefs when necessary)
!!pbIai (A) Incorrect, turbine load will remain relabvely constant with IMP IN (normal at 100%). Reactor power will then lnswii
- increased steam flow. (B) Incorrect - selecting Steam Pressure increase due to Mode will not close the steam dumps if the failure is in the valve JJ will increase due to increased steam flow, and either Steam Dump Bypass Interlock switch in OFF/RESET dumps (train A&B) will close alt steam
_ ._ _.. __ ___ ___ __ = _ __
= _ _ =_ =_ _ _ _ _
=_ =_ = _ = ___ = __ _ __ _ _~.
Refrence This FacillytReencrellu irwd Big Notes r Setiont 1iRefer Page No. 'ev3.o. Numberj!
_ _ i Steam i-_
_ 1 7_
ilIi ___*r___
I MarIal Required for Examination QusinSuc: Ohr Faaity Question Modfcto Me~fiod: _E~ntyMdfe Used During Training Program
'Question Source C nt 2001 Prairie Isiand Comment Type Conr Comrmnt etTReVfesCOmPlete
=_
- -A
~y Lf77~
-- ltn
-CI Pelr
-I Supervisory Facility NRC
Question Topic Main Turbine Generator (MT.G) System Once every 31 days each of the 12 extraction sleam nonreturn check val.es are tested by observing freedom of movemnt of the weight arms on each val.e This testing is performed to ensure:
- a. Steam line breaks which occur outside the Auxiliary Building are positively isolated
- b. Flooding does not occur in feedwater heaters.
limitino the ability to restart following a reactor trip C. Excessive overspeed of the turbine does not occur following a turbine generator trip
- d. Overpressurization of the main condenser does not occur if feedwa:er heater levels increase too high Ans r. C =,m ICoeignit veLevel [~eorve 1 d- E 7
_ = /19 /02j KA:J 045000G225 j;2.2.25 ROValule: 251 SROi OValue:J 3SYS 1 ! iRO Gu P R171GRaetip:
°[ 3 11 [1.7Il!-----up 31 SystemilEvoldine TItj MainTur r toneyGeneraor=Syste
___ 045 lKnowledge of bases in technical specifications for limiting conditions for operations and safety limits q Noniretum check valves (12) are part of the turbine overspeed protection circuitry and thus protect following a normal turbine trip. specifically from the turbine from overspeed steam flashing in feedwater heaters from reentering the MT. (C) Is correct. (A.B.D)
_. . 1* Gvo ueweGVwGGGV@VGii --
avidGlV 1~___ ~ ~ Ti ____ 7X K" Pl bl r1 Tech Specs - TRMV FTRM 33 g _ TSR 3.39 2 _ g-2 J-Old Tech Spec Basis Doc J[B 3 4 3-6 __ _3 Turb O - 6
__ __ __ _ --- iX~_
,r__ _ -z-z 1 _-
ew Modlflceuln J___
luesion _Metho: _____Ie~D
§ n~r~agp~rm1
~.Uoin ~Socem ~ls
-- s ------ -- -- -- -------------
_____ _ _ _ -- -- = -- ~-= =__ euPsvhsoryJ J Facility NRC
Question Topic Main Feedwater iMFdj S stern The following conditions exist on Unt 1
- Reactor is at 100% power. steady state
- All control systems are in automatic
- Instrument Airis lost to one feedwater regLl iting valve 'FRV-510 If no action is taken in response to the FRV wArch of the fct owing describes the response of the plant operator? AND tolloAip action required by the MCB
- a. 'TURBINE TRIP ABOVE P-8 trips the reaclor All Main Feedwater Pumps AUTOMATICALLY triO Operator Isolation AUTOMATICALLY occurs must simply VERIFY Feedwater
- b. TURBINE TRIP ABOVE P-8' trips the reactor All Mlain Feedwater Pumps must be MANUALLY tripped close all Feedwater Isolation Valves in EP-0 Operator must MANUALLY
- c. "S;G 1A LEVEL LO-2 trips the reactor All Main Feecwater Pumps AUTOMATICALLY
!Isolation trip Operator must MANUALLY close all Feedwater Valves 4
- d. 'S/G 1A LEVEL LO-2' Inps the reactor All Main Feedwater Pumps must be MANUALLY tripped n Feedwater Isolation AUTOMATICALLY occurs EP-0 Operator must simply VERIFY lAasw.i d m19/0] j CognifwiLvel 3 [ipptication
_w _ , , AIl ~o j acrjidwood ra o
= _ - 7/19.01 7 21 CA 0 A212 J A2.12 ROVahs 43 i.O VaOVakio E YS R Group:- L SROGroup:J L Main Feedwai erSystem ___
Ablt to (a _
059 Ability to (a) predict the impacts of the following _ __ _
on the Main Feedwater System and (b) based to correct. control,or mitigate the consequences of on those predictions, use procedures those abnormal operation:
Failure of feedwater regulating valves (D) Correct - FRVs fail closed on loss of air SG level wilf decrease to the lo-2 rx trip setpoint. Lo-2 level does not trip the MFPs. P-4 lJinitiates FW isolation. (AMB) Incorrect - FRV fails closed, levels decrease. (C) Incorrect - Lo-2 level does not trip the MFPs. P-4
.3 I..a. , fl t ijj~_ Refewsnce TMi InA-e
_v*
Annatr-K ---
Facility Refetrence =
NumbrJnfStI~ TPage No.] -"6 1 .1 ruiatoresponse proc SwIf
_JIBWAR1 -1A Fwd iNotes 1 _
i- 8 I ,J i
4iiJF~
I_ _ _qudor~mnj J______
0 _ _ _ _J______ jj]
oNew J QU istion j u U UefidaDuring Training Png
.no~fb .__ _ _ ___ ____I
_ b __ = n t ~i =p i _ C n t__=
1 ju viso eR
_- inry r- -F-~ ~ - - r-- - -~ - ~ - -- - -- ~ r o
-~-
- - IS~ e VI~
r r=_ _ac ivty
':NRC q0
Question Topic Main Feedwater (MFW) System Al 50% power on both units the Steam Generator programmed level for each unit is Unit 1 Unit 2 a., 133 0% 36 3%
- b. 50.0% 50 0%
C.. 60 0 % 63 70/-
d.j -8 0 =- 80 8% -- - - _ = '
A nsi ar! [I iiE a ~e R J~CognIflv.LoveI j Aoel _ro _1 C Me oy - J a t J[ r d o d I Faiiy FiR,~o Eam Xl 7/19/0g JC FZ p059000A302 j A3.02 OValu:;Ij 1RO Value: 1 j [1s etL] ,RO Group:j f J SRO Group:J 1 MainFeedater System _____
. _ _1___ _,_=___
059
'Ability to monitor automatic operations of the Main Feedwater System incduding:
_,__=__
Programmed levels of the S/G of4 Program levels are U-1 at 60.0%. U-2 at 63.3%. from the lull range 0 to 100% power.
(C) is only correct response 1'-"- 4- aci l R2eec Nume ISGWLC LessonPlan S_______
= j 1FWX 01
_ 1! i 2 j2 1,
--- -_i__J 11R hr n J I 1--_W-___-_1 - -- ____J
_ 1, _ _z _ .- ------ _
____ ____LSupervjory v t I . _ ._ __._.
i Facillty
PO SkyScMaer I SRO Ssraag I ROSvst.m utvoLROution S _ tnL Outine Changes G iu 33 Question Topic Main Feedwater (MFW) Systemn The following conditions exist on Unit 1
- Preparations are underway to perform a reactor startup per I BwGP 100-2. Reactor Startup-
- Steam Generator levels are being maintained utilizing tempering line flow via 1FW034A-D and 1FW035A-D
- When testing the reactor trip breakers per step 13 of 1BwGP 100-2. 1FW035D did not automatically
- 1FW035D was manually closed by close the NSO and the condition reported to the Unit Supervisor
- All other feedwater valves responded as designed Given the above failure, per Tech Specs the reactor startup will
- a. Be ALLOWED to continue with BOTH 1FW035D and lFW034D controlling tempering line flow its required position, the safety function will not be Since at least ore valve in the line isolated to challenged
- b. Be ALLOWED to conbnue, however. 1FW035D must be declared inoperable and dosed with power removed is then allowed to operate indefinitely in this configuration from its valve actuator The Unit C. NOT be allowed to continue because BOTH valves in this line must be OPERABLE to ensure positive leakagein the event of an accident. isolation and prevent containment out Ld NOT be allowed to continue. In additon to FW035D inoperable which precludes any future Mode being inoperable, the Aux Relay function of feedwater changes untl repaired. isolation must be declared Fr j Comprehension !~ Bradwood E1i1 T 9/02~
7 059000G133 I j 21.33 WiVa ius' 3-41 I 4j 1 ISYS I 4I33 iO6roup:] 1133 l Main Feedwater System l059 Ability to recognize indications for system operating parameters which are entry-level conditions for technical specificabons.
(A) Incorrect - in order to perserve the safety function, 1FW034D must be closed with power removed - single l ~t_
- 3.6.3 does not require mode reduction if the failure. (B) Correct -
required action is completed within the time allowed.
VFU-m t I. Sqssujvgua
- -SS_-v*
- c;autAS Uov00 *,tJS S-(C) Incorrect- one valve may be c JCa.j, the aux relay function has not been affected. S S R~~ N M~
ReRreoeus.l___ umI2
[ ^ 111
- n pecs l332ESFAS Funct5 II _ - ------------- I - --
Al a2-x12
! 7 i lNew 1 ~ sniij PLOP_____
il1i -- 1i- = I
_____1 forrvor IF- J-- -----.--
al NRC qj)
Question Topic ALxiliary.! Emerg ency Feedwater (AFVW) System The FIRST signal to automatically start both Aux Feedwater Pumps onl each respective unit is received as steam geoerator operating tevel through (1) level passes fromn normial 3/4on Unit 1 and 121 on Unit 2
- 11)(2)
- a. .12 0 22 8
- b. 18 0 36 3-c.! 23.0 41.3 d.: 88.0 80.8
~i~r3Ij i Anwr_
Ex~mLevl] F' 'Cognitiv evlj e! facility:1 Braidwood I"cio: ~s
__ ExamDate:.J O rupj 719/02' R~opJ~
F(5 1OiOOK1ioi K1i01 RO Vaue:]I [4~l 'S 0Vaiue:- 1Lialo:Iry O ru: ::1 Sselouto hjfuiiriEegnyedaerSystem ___ __-________f061 ftn~~.Knoiede of the physical connections and/or cause-effect relationships between Auxiliary/ Emergency Feedwater System and the
~~I n]LO-2 SG Levels (2/4) w autom~a ul tcll srtbtA pupon each respectiveunitLo-21LI-i181.0%. U-2=36.3%
J Faifltotenelil~ w.J]W~rne S~ect on *Pgo~ N-rinuncialtorResponseProcs BwR1/2-115-05i _ ____ __1 7 -___
siiROeq11r*e~r Exaawlnmuon I _ __ _ __I_ _
New- J~uet~o Moifcaton ethd: JUsed During Truining Pmogrm onmnt Type] n n jNRCI
Question Topic Auxilia'y , Emergency Feedwater iAFW) System The following conditions exist on Unit 1
- A reactor trip turbine trip has occurred
- The crew has Iransitioned out of 1BwEP-0 to 1B~%EP ES-0 1 Reactor Trip Response"
- Step 2 is being performed. "Maintain RCS Temperature Control"
- All steam generator pressures are at 1050 psig a-d decreasing slowly
- All steam generator narrow range levels are < 10
- RCS temperature is 553 F and decreasing slow..
Which of the folloaing actions is 'equired to control and minimize the cooldown of the RCS9
- a. Maintain maximum AFW flow until steam generator NR levels are >25%, then decrease total AFW flow to 500 gprn b.: Decrease total AFW flow, maintaining >500 gpm until SG NR levels are >10%. then throttle as needed to control cooldown
- d. Stop the AFW pumps. if operating, and isolate them from the steam generators
~AswerA- _ Ib~ 'Eiam Lee ~ I [Apphcabqn
-CgiiLevevel ,, _ ~ a~ _ yI[ raiod-- - ExamDate:
- - __ . _- 7/19/02 061000K104 JK1.04 1aw: j 3f SROVa j.
~~~ouin j ~xlay-- ---
- ct[n ROGroup:; 1J SROGrouP: uRp Li
_ l _d Auxiliary/ Emergency Feedwater System s - -s- --
l 061 jKnowledge of the physical connecbons and/or cause-eftect relatonships between Auxihary / Emergency Feedwater System and the RCS per 1BwEP ES-0. 1. step 2 RNO. Maintain total AFW flow >500 gpm unbl NR levels are >10% in at least one restrictions are place on AFW flow rates. (B) Correct SG. Then no further (A) Incorrect - 25% level & 500 gpm are too high.
(C) Incorrect - cannot
__ __=~ 1 L ____ ]ub 03 iecioe 1#ag No-1 iRevIisf Z.i ~
r Tnp Response &Bass JFBwEPEs-o =Lsp2RNO _
P r I 1
= --- =- -
_ = :L-
-=---=-
J4-f- _ -- _-<J u L1 _. _
<1 C:
l0 INNRu edored f xaor Exo __
od LU1d _ urngTr1isPmgnm -- -4.W 8om entType 1 Comn -_
g __ _l S ___ _ 'Revr . ~~t f
j f cblity
., ,, _- - - -- = - -----
=___Ii_
!ii-- -- -- .--
j= - = -=- -- -=--=- -rV~
= _ __,-- NRpCisoryi NRC
Question Topic A C Electrical DistribLtion System A loss of all AC power has occurred on Unt 1 The crew is performing 1BwsCA-0 0.
-Loss of All AC Power- and is preparing to cross-tie to Unit 2 using a limited crosstge to ESF BUs 241 DG 2A is supplying the bus You have been assigned to monitor ESF Bus amperage as loads are restored on Bus 141 Which of the following loads will draw the largest running amperage?
- a. 1A MCR Chiller
- d. 1A CV Pump Exam Lov ell _ Cognltve ell '-Memy j !Pacflf: rai-._ Exam ICA: 0f62000A30t lFA301 ROValue: I o 'SRf -alue:-I F3' to:; SYS J ROGroup: l B Gu AystermJ-Evokilon Tltij A C Electrical Distribution 062 onitorautomatioperationsoftheAC.Electrical Distnbuon ncluding =:_
,Abiitytm Vital ac bus amperage chiller dra ps (B) Incorrect - RCFC draws 14 amps (Lo speed start as all drawrs 156 amps (D) Incorrect.-1A CV draws 63 amps ILossofAI AC-ConbngencyProcedure j 1BwCA-0O llsteps21.40,18,24 1 l j l10uo 1 j Loof 4KVESFBus __ J 1BCwAELEC-3 J tepa achA J j r r _ -
FH- - --- --- - ------- - --- --- -_--_-_ _ -__
1~ ,,
l_ _ =
Ljomn~ __
ItType _c- _- __ ------ ___ -_ -.
_-_-__r_--___
- - I eviwe ConMplet _
Lomnt- _
F- j- __ --- -- =------------
if I_ _____ __
__'Fc~l NRC
RO SkvScraper D SRO Skyucraper l RO SystrgJEvokjton List SfO SytVEvolution Lst Outline Changes j .
Question Topic A C Electrical Distribution System A reactor trip has just occurred on Unit 1 The automatic bus transfer (ABT I failed to operate for Bus 156 Which of the followxng loads is now unavailable?
- a. 1A Motor Driven Main Feed Pump
! I ____ e B _
Examov
_ _ ___caton _ C 711910 2 1 1 l! <
v~
I I
n Jjff. ~adod ~una: l~ -~-7/19piab W l06 K201 lIJK201 ;ROVIif 33 F--Oai- j
.I 341 lSYS I ROGrOUP j SROIGoup: 2]
k"Fufton liii A.C Electri a Dlstibut1on 062 mVienimt e of bus power supplies to the following:
Major system loads of (A) Correct - powered from 156 (B) Incorrect - startup FWP from 159 (C) Incorrect - IA CD/CB from 159 (D) Incorrect - 1A HDP
_ _ XF lb.e 1re e _lSection l ]
No-j i ubi l1-AP-XL-01 1ACDistributionLP 1I _29.30 ll 12 ___
~~~~xrry =;=mjr=- -Lj_=XIL I Requbed for Examination _----_--
ExamBanMeath m UFaclity Method: lDirectFrom Source Jf r i Pr jIa on_ -C e 1 2001T Bwd NRC
- Cdia~titl Tpe II # _; I!w Comment -- :
-~ I~l o
, Ievscoit
! -- - -- Facility NRC
S SRO Skncrak Question Topic RO SvMenVEvoton Lit D C Electrical Distribution System l SROSvsteerEvolutionlist I OutlineChanaes l i i Which of the following describes how a Reactor Trp Breaker .vll respond to a LOSS of 125 VDC control when the loss of control power occurs) poverO (Asstrne the breaker is closed
- a. Trips OPEN due to loss of power to the SHUNT coi'
- b. Trips OPEN due to loss of power to the UNDERVOLTAGE coil C. is NOT capable of tripping on a SHUNT trip i'is NOT capable of tripping on a UNDERVOLTAGE trip J~nsweitya:t l Plicaio;1 nJl Fdraidwood _t
.. uwuteIo l7/1 r 2 E ]r=9 l063000K20 K201 rRValue: I WOValue:
[5 3.1 Silon: SYSI RO Group 21 OGroup G T D CElecticl Distribution -
063 IKA Knowledge of bus power supplies to the following: -
Major dc loads A. IncorrectbeaethsuncolinomlydeerzeB&Dinorcbeueteuerotgcolisulidwh48
~~ ~power from SP
_ww i4izReerne Two ite 'f acillity Refeirence Nume ]eeeneScto [ije fti~ LRetlJ7*R_2iR Wl~dndFLA .Fumber'I O.NmeI Erical Prins Solid State Protecton System 20E-1-4030-RD6 IN/A J l l-RP-xL-o4 t _ I9 lO '4.110 ff - l E l I I__---___-
Faclity Exam Bank l etlon od t _l _ d Dt~g Trakg Pm1l Sco NmehNJ 200 Bwd NRC. 1998 Calloway NRC Exam i
Comet*p I
-____ --- - = __ _ _ E--
-_ -r ------
=---_ __e r~~~~~~~~~-~---.-~=-[----
z----- =---- -- -- -- -- ----- =--------=-
.- -- =--T
-~ - - -- 'facility
_NR C .
Question Topic h rr ',y Diesel Ge ieralor (ED G) System When synchronizing an Emergency Desel Generator to an energized ESF bus ini-ediately after closing the generator Output breaker EDG to 500KW by going to (1 on the Diesel Generator load the1 (2 i I 12)
- a. Raise Governor Ad ust Control
- b. Raise Voltage Adl ist Control C. Loower Governor A-JLst Control
- d. Lower Voltage Adjust Control Answer a I Exam Level [B Cognitive Level Applicabon J Facily: Braidwood _l9 E02mD eJ[ I 7_
KAdi06400OA108 Al 08 ROValue 31 iSRO Value: i [i41 Section: SYSJ IROGroup:j =2jSROGroup: L2J Sy*rn/Evoltjon Title Emergency Diesel Generators 064 I Statment:
lA Ability to predict and/or monitor changes in parameters associated with including operating the Emergency Diesel Generators controls Maintaining minimum loadon ED/G(topreventreversepower) l() is correct. (A) Incorred - lowering DG Speed will decrease load, approaching the reverse power trip setPoinl (C&D) are
- Jis incorrect - adjusting the voltage control will not affect DG loading
'rencoltb esGeneratorStartup ReferenceNumber 'Reference n L _ E jNUir r
- BwOPDG- i F 1.3 2 _1
-~--~ - - - = --- -- r--------------~-~-~-----~
- - --- -- =- 7~-
Ma "F- __ -quirdUo _____
~~~~~~-- ---- -- I-to Dirga 71 Qusi~on Source: New ___ j O i~HoniCatWo Metivtod: K i 7,&~'w __ . __._ __ _
Proram Question Source Comments IcommentType Ccommnent Pla-
-t
- --- ( =- -- ------- = _ - = - -_
==__=___=.___1
- r- -o
-f yC;plt Fb-r-':.:.....
_..__.. ___.I
,ew Facility NRC TO
Question Topic Liquid(RadC.aste Sstem (LRSI What TWO conditions will INDEPENDENTLY cause autorna?'2 closure of Liquid Radwaste Release Tank Discharge Key Locked Valve 0WX353'
- a. Low circiflating water blowdown flov and high radiation sensed in the CW blowdown flow
- b. Low rirculating Aaler hlowdovn flow anC high radiation sensed ir the release header
- d. High release header flow and high radiation sensed in the CW blowdown flow lnaer, , l Exam Level I B_
Coonitive Level IMemory Facility: _Braidwoo__Mileb r ,902 rij
_=____- _______
-i68000A404 i A4 04 'RO Value:]a F8J SROVa lue: l r3 71 cton: I SYS j RO Group:j [SROGroup: I 1J System/Evolutlon Title I Liquid Radwaste System = _ _068 S at-mmjI Ability to manually operale and/or monitor in the control room-LAuntomatic isolation
-'_" __ I __ .- ___. .. 1 Wuvjueu I
I l.Lquid radwaste re ease form j[Z'OPWX-526T1 j;22.33
_E.G 18 l -
1_ = _ __ == __J I - - ._ --------
_ __ V-__
I_ _ =_ ____ _____ H---
I_---___ ---- ---------- _--- - ---- -------- J------- __IZZIZL Ir_ __jl __
!!larlt l Reiquird for Ex!aminatIon
~sinSer _ _
laclt xam Bank__
-I_ _
_ _ wiia
_ w 0_
QusinMdction Mehd 4_ __
ditonally Modified Ue uigTann rga
¶1
[Fon Source Comments 1999 Bwd NRC
_lhi _ _ _ __j__ ......
Comment Tpe omment
___ __ _ _ __ _ Su_____pe rvi ory]
- - J- -_--= - ! r _ _=___ _ FacIty
- NRC
. . . j N.
RO SkYScrawed SRO Skyscrawpl RO SvtriEvokfo l SRO Sstn*EvotonLust Outline Chanil .3cial Question Topic Liquid Rad.%asle System (LRS)
An operator spent 30 minutes in a field of 150 mr/hour lining up to transfer the contents of one liquid radwaste monitor tank to another He said la-e-that if he had 'preplanned' his .o~k he could have been finished in 20 minutes How much dose could have been avoided if he had preplanned the job?
- a. 50 mrrem
- b. 25 C. .12 5 mrem
'i 10 5 rem[TOr
_ Ofm___________
___ __ - 7 1
-tJFKZ, R Lovel rxam R Appficalion a Irwood3 im* = __ --- j 1068000K503 K5.03 1 KV5ue R IV j;SROValu .6 lSYS j ROrp:' uJ O i
!FlIut~o Title [quid Radwaste System 068 3: i Knowfedge of the operational implications of the following concepts as they apply to the Liquid Radwaste System:
Units of radiation, dose, and dose rate 1omr min x 20min = 50mrem if done in 20 minutes. Savings of 75-50=25 mrem (B) Correct
- __f-We__ . [
_ _111,11111e 111 I .umberN 1u oteRouna. _ r__u
[Health Physics/ NGET - l __I I I RadProtectionLP _ ____FPractce problems j 1-35 8 i l I
AlRure for Examination _ ___
soua.- FFacility Exam Bank Juti Editonally Modified l UIeDriting Tmln FP9og ram orcMATe ormimen 7! T
_ ---- I Commentl
_u_
L_
I_ __-
r--- - -___D__ __ __
1y ---- r----- -~-------_- _3-i
,Facility I NRCl
Question Topic VW.-,tc (Gis Disposal System (WGDS)
Which of the following REDiJ(.ES the Possibility of an unintentional radioactive release to the atmosphere relief valve lifting? from a Waste Gas Dec.iy Tank lWVGDT~
- a. OGWO014. Waste Gas Discharge valve, will close automatically on detected high radiation in the discharge header isolating tVie relief path
- b. VVGDT relief valves discfharge directly to the vent header so that flow is directed from the online tank directly to the standby tankh
- c. The waste gas Compressor discharge pressure is automatically limited to less than the WGDT relief valve pressurre setpoint
- d. WGDT inlet valve closes automatically on high pressure isolating the on-line WGDT and directing flow to the standby WGDT Answer _d Exa LeveW B j Conive Level 1A~Pfcat--n FBraidwood __ J ExamDate: 7/19/02 1
i.071000K305
_st__lE______ b jI K3.05 Waste Gas Disposal System
.i!j 321 ' j S -7
_S__tllun RO Group:j J SROGroup:j 1j
-KAStsmjEVOI Knowldeont 071
__fttata`-oso mafnf-ono-h Wae____
KAS mGas _ ___ -_ _
DisposalSystemwillhaveonthefollowing:
ARM and PRM systems l Exp aton of (D) Correct - tanks are automatically switched on high pressure.
l were:w j relief path is not isolated (B) Incorrect - discharge (A) incorrect - al reliefs discharge downstream of OWX014 so the is to the plant vent (C) incorrect - discharge of the compressor has no affect on Referece Tile - ] rFaclfty RAe ie Numer [ etii v6i] l Gaseous Radwaste LP -
j l1-GW-XL-01 '-- 12-14 F6id Big Notes i RWE- - -- _ - f ' __
--. =__ -_ Jt __,___ iZii§iF Ii
',.auetlon Source--_
Comments I j1999 Bwd NRCj I_ _ev_ _aip.
11 r -
t
'Per --
L-g=-_.
-T-
~_ .= I i~ - _ __ _ ____ __ _up rvi_
Facilifty NRC (O(
Question Topic Area Radiation Monitor "g (ARM) S~stem Radiation leve's in the Fuel Handiing Build rg INCREASED causng BOTH Fuel
-Aaniding Incident raoition moniotors (AR055 and ARO56I to simultaneously reach their actuation setpo-nts Which of tie following would AUTOMATICALLY occur due to this cowiilti)nQ
- a. B Train FHB Charcoal Booster Fan starts. then A Train FHB Charcoal Booster Fan starts
- b. B Train FHB Charcoal Booster Fa i .v l start ONLY if A Train has failed to start
- c. A Train FHB Charcoal Booster Fan staits then B Train Charcoal Booster Fan starts
- d. A Train FHB Charcoal Booster Fan .%isistart ONLY if B Train has failed to start Answer Id Le.vel IF emr - i-t:IFrrw71/2 J Exam Lavel B_ Cognitive ory facily raidwood j ExamDate KA: l072000A301 J A3.01 ROVatItW 22] SROVIlue: i 311 Section: SYS JRO Group: j [RO r0Group: f yStIMIEvoltitn TIb I Area Radiation Monitoring System 072 lnt: [Aility to monitor automati operations of the ARM system including :
Changes in venbilation alignment F rW A^.Inorc.Dmper interlockis prevent both trains from starting. B Train gets a start signal first When l ' position, an interlock preventing the start of A Train. B. Incorrect - it is the reverse of D. the correct answer. it'sats ts damperl C. Incorrect - B gets the
! Reeec _
i3L ft' cii~b~
aiFtYdwR~fnceNwnb~rj~s~.
- 3ge NO] Rev iso ~Nftmbeil Norse Notes Aux Bldg Vent FHBinterfocks J[ i lSys;tem LP CH 43A :Jr -5 = _
___ _ __ _ _ _ . 7
_ . .-- ~- . -_ ._ FII_. J. JI_ - l Quemtion Sourc Commr e 2001 Bwd NRC Comment Type J _ __ w omolmel r---- --
-- - Supervisory I 1
-Facfliy ;
- NRC
RO SkvScrapef SRO Skyscraper RO SstenlEvolution List I SROSntemEvobtlonList I Ouftine Changis Question Topic Area Radiation Monitoring (ARM) System The detector for 1RT-AR't 1J Containment Fuel Handling Incident Train A Rad Monitor has fa led caus ng the output of the mnonitor to 9o t,9ih Which of the follo,&,ng automatic actions will occu- as a result of this failure9
- a. OVAO-tCA. Fuel Handling Charcoal Booster Fan is started
- b. 1VOOOJ4A Containment Mi'ni-Flow Purge Supply Isolation Valve is closed
- c. 1V0003. Post LOCA Charcoal Filter Isolatlon Valve is opened 1
- d. iVQOO3C. Post LOCA purge exhaust fan is started I lAnswer I b Exam Lrl [Bj_ pnfthve g Level [(Memory _I Facili Bradwood EamDte J _r _7/9 KAJI [072000K401 K4.01 RO Value:W 33 SROV .u:; i36:1 SOction: SYS lRGroup.j jJ G-ou roupj 9J
[IistlEvoIution TMtle Area Radiation Monitoring System 0- 2 1K Knowledge of ARM system design feature(s) and or interlock(s) which provide for the fotlowing:
Containment ventilation isolation (A) Incorrect - this fan is started via AR055&56 skids. not AR1 1J or 12J (B) Correct - this is part of the cnmt isolabon signal
^ J. Igenerated. (C&D) Incorrect -these receive no auto actuation signal from any rad monitor.
Faciry RPsr no- Numb Nuibor]! noiSctJ.n No:. [Rlon u lmbr lRM.11 annunciator response BwAR4-1ARO11J j B 1 2 j jBd,,u-- VP - ____ - --_ -
1- - 1 5 _j1 SoY
-Sotitn [Facility Exam Bank__Question Modfo nMehd J
_Signifanty Modifiedj~ LeeI Du!rtingTraning Progrm -
-- _.ty NMC
Question Topic (Circulating Water System The followirng conditions exist on Unit 1
- A loss of all Circulating Water Pumps has occurreC due to excessive grass collection in 'he intake bay
- A reactor trip I turbine trip was manually initiated by !he coerators During performance of 1BwEP-0. a SGTR occurred on the 1B steam generator
- The Crew transitioned to and performed actions contained in 1BwEP-3 Stenrn Gener7 or Tube Rupture
- The RCS cooldown and depressurization steps to equalize RCS and ruptlired SG pressure have been completed
- SI was terminated and th erev ss now investigating the appropriate post-S(;TR cooldo-wn method to use
- While investigating cooldown options. RCS subcoolinq was lost
-Additional ECCS pumpps have been started and aigred. but subcooling is nrot recovering Which of the following procedures must beused to continue the post SGTR cocldowii anc recovery ictions from this point?'
- b. 1BwEP ES-3 1. -Post-SGTRCooldown Using Backfill" must be used quickly to recover Pzr leveland subcooling lC. BwEPES-3 3 Post-SGTRCooldown Using Steam Dumps must be used as this is the preferred method of recovery !I
_. _ : _-f .- . , _ _ ,. _ _ . _, _ _d __, .
d7 BwCA-3 1. SGTR With Losso Co t ,Reatr Subcooled Recovery Desired s they option available and must be implemented Anawl r J [Exam Level ognlive Level
- Cj Applicaton l Facility
- j Fraiwood w I 7/19/02; IMA. FO750006~06 l9 !
2.4.6 owlyijW-6iH0lCuculating Water System RO Value:
c 322 r 1 SRO Value I1 1jSO4
~
L on _
i ~
i SYS R130 ru:~ Otpir FR~le 9 jSlR0. pP3~ C 0 75 Kptom based EOP mitigation strategies.
F(A) Incorrect - step 38, Go to Appropriate Post-SGTR Cooldn ethod, is the LAST step in EP-3. There is _no continuation from tnSwers: here without a transition. (8) Incorrect - OAS and step 2 of ES-3 1 require transition to CA-3.1 with the loss of subcooling. (C)
- i. 0;
- SUB*
tJ *%3 U'O V *. . .i tif.V W C C
- bEs.i UB*J.. CA,1^lli USC OJPG COB. .4,q
. O zZS I JC***. .LI s .i.i *t - OS MB G C.. CV V each procedure's OAS and step 2 in each post-SGTR cooldown procedure.
_______ __N_ __ _,__ -_
EOPS =-SGR1BwEP3 p38-o AS__ =5 4____ F1 00 I~ost-STR1 Cootdolwn proceu resj
! 1Bw3P3ES 3 1 & 33 I =HSTeP2aoAS 1____
P-3BasckgrounDocs MIaterial Required for Examnton J _
jusinSuc:
New ___ jQuestion Modificatin Method: J uring Trainingninn0 Progrm' l- = -o = -- - -
__________ib Question Source Comments Comment Type J Commnt
- - - vlewsComplete I SRO ;' 'Assessment of conditions - selection of appropriate recovery procedures I
I
- -Supervisory Facility NRC Io4
Question Topic Fire Protection System tFPS)
'Which of the following Fire Protection subsystems is used to provide coverage for the 1fAuxiliary Feedwater Pump?
- a. Foam
- b. Water
- c. Halon d.1 C02 nsr jd J iExam Level 1 Cognitive LevelfrMemoryd ___j E a tl: 7/
-,BJMmr Facility: ra -- -1F - 7 Oi
,KA:: [:86O00K103 KI ROValU.ri K103ISROVat Section: !SYS j ROGroup r I Group: J ytEvolun fFire Protection System 086 Rkilaiemirnij [Kno~w~ledge of the physical -[connections and/or Y in cause-effect f l m relationships n _
between Fire Protection System and<thefollowing: - - _ 086
- AFW Systemn plmnaflon of](D) Correct It __is_the =only ___ _ _
FP system in the lB AFW Room __ _ -_
_ _ _ _ _ _ _ _A ___
Bwd Big Notes
[re Protection LP l __P2 ____
11 Jl J- _ _FPX---- - I
,_.__ __ ____ ._ .r ___ rj_ _____
terla Reuqtired fr Examnfnton
__ III.
_J _
j _ 1 fetlon lore lNew__ -_-_- J .. eto: - 0 lse __ Dun Tranin P~brora
°*I* S - C nts '- - --- - ___ ___S_
romment Type I ,ment -
___ _ _ _ _I_ _____
- _ ReveWS Comlpet rI - r~---- - =-_ -- =----_-- _ __ _ ___ _ er I I _=_ __ Supervi Facility
'iNRC (3s
Question Topic Fire Protectson System IFPS)
In which ONE ot the following aireas is water NOT used as the primary fire supression agent?
- a. MPTiUAT!SAT transformers
- b. Upper Cable Spreading Room C. Hydrogen Seal Oil Units
- d. Ventillation Charcoal Filters l Anserl ,
L ameVol CognitveLevel l Memory _ Facility: raidwood J l'aDats:
_[8600K3 I K503 RO Value: I 3.11 SfOVaI r4 Section: sYS ROGrouj 2 j --
.03ii.
_ _ e. JI -G roup: 2 LSYtnVEVOIUton.Tl#& [Fre Protection System -
__ 086 n Of the operational implicationsofthe following concepts astheyapply to Effect of water spray on electrical components
- water is not used where damage may result from spray on equipment. is correct answer.
t _Rebr.n s < S FacRity 1 u S octnibon Bwd Big Notes - Fire Protection JfFP-2 J Jrr-__r_-----I r -= - =-_===--- --- _------ -__-
j!!wbl Requa d br Ex.ng ia--
~Sure FNew7 J eUohifcunM~ = ==
_ = ___
-v J Drig Trainin Progrm7 ComntSoipe] Conmnt - - __
- =_____ !upervisory
_Facility !
NRC IOUe
Question Topic (Ger*rc In accordance Nith the Pre-Job Briefing Checklist which of the following is NOT rie of the 4 Key Questions asked7
- a. What are the Criticai Steps in this task?
- b. What are the Error Likely Situations'
- c. What Defenses are we relying on1
- d. 'Who is in Charge of the evolution; LAnswer jd I Exam LeveljR I !Cognitive Level -lMemory Facility: rBraidwood mDate: 7/19,'02' Fi94001GO10 21 1 _ RO Value:7; 3i Setn r-- ROGfroup l ROGroupl_1l
&bt!Tfvolutlon
--- v-------T- Tillbe i----- -------- _ _GENERI --
jC Stiatemnt: - --.-
=Knowledge of conduct of operations requirements, Vnatiison off (AB.C) Incorrect - all 3 are included N :W~sConrect answer - it is NOT included. on the pre-job brief checklist. The fourth is 'What is the Worst Thing that can go wrong' Jj (D) is
-Refwaance TW*g f -
i Pre-Job Heightened Briefings _ HU-M-121 1 _Attachment1 J1 l l° -
1~~~~_ - -e -~-_-------~J -- i " __ -- !-
-_ _ __-__ _. ___r __ __i__ - _
blai Requlred for Examninatbon -
e . -New -o-M-d-on metod: _ _ D T _.gProgm 9uUon SoutrceCotmments rommentTypej ant C_=lCornp iit-=-=- - ---- -_=- -=-_=--=-= _ __, __,__Sprvof K- ZiT~ F7 71777i7~' ~aiiity NRC I.-- -
Question Topic Generic In accordlarie Nith BvAP 320- 1 -Shift Staffing-, the MINIMUM shil't staffing requirement to comply .,ith Tech Specs with BOTH units at powver include RP Tech NSO
- a. 2 3
- b. 2 C. I 3
- d. 1 4 Answr, ~c Exam Level S j gntiv Level Memory Facility: 'Braidwod__
L Eam I.
_ae o
'kA:l r1940i1G104 1 . 23 R 3Vle 4j LSecn:a E 7/19/2 a~: pW ~
ROGup:; it SROGroup:
'SYstemlavolution Title ___GENERI K ..-
'Shift Staffing Tech Specs
[k frowle~~eofshift
~acPamaionoJ~
C) orret -perTS staffingrequirements, 3.5.2,a RPTechshallbe onsite when fuelis in thereactor.3 NSOs are 32-1 2JJgnatn C
required per50,54 52 _ F= 1 MOWMIa Requiledll for Examinationi Qustle~~~
Fc~tt Exm an IQustonModlification Method: Sinfcnl Mdfe sed During Training roga QuesotinSue Comrmenlts; 2001 Bwd NRC JRmeCom ISRO I FTS Admin5.2.2
.17. 71.11K71 ___I
'Facility
'NRC
Question Topic Generic In accordance with OP-MA-101-1 1i Reactivity management Controls-, which of the following NON-LICENSED individuals can n-anpiiete the controls of the reactor if under the d rect supervision of the licensed Reactor Operator 9
- a. An individual enrolled in a apcroved training prcgrarn
- b. A System Engineer di.rng Su. eilance testing C. Any Non-Licensed Operator during surveilance testing
- d. Any individual directed to operate controls by the Shift Manager nwr a j Cognitive Level IJ[emory ] Facflty: ifraidwood _ ExaMat: 7/19___i A: l194001G109 _j219 LOValu: i SROVaIu:j +/-9J Sctlon [ G J rROGroup:I jj SROGroup:
fLyst InEvolutn Tite ____________
GENERI KA Statema]_-i---.
Abiliy_to direct personnel activties insidethe control room.
planaton o; l(A) Correct - per the reference, must ensure trainees manipulating reactivity controls are enrolled in an approved training program onew : u and directly supervised by a licensed individual (B.C.D) are then Incorrect R .oli il-_t F-Rt""i 'L6-. -wg RactvityManagement Control J[P-A -103-104 3.53 J 1 0 . _ I Reactivity Management ControlLP 7r IPBG _ NA - J NA o2 0 --
"atefItl Requ d fhr ExafMna j .
IQuelto~n Souce: Failt Exam BankJQuslieftlo Mdkediiciln atod Editonially Modified J~e uigTann rga uetin Sour C nIS 2000 Bwd NRC 1996 Bwd NRC Tomment T r_ _ + h 1Ž wbw Comphpte_
icyi
RO SkScraper I SRO Skyscrapr I RO SnytenEvolution List I SRO SmtntEvolition List Oulinae Chanqes l ;&..
Question Topic Generic The Unit 1 NSO is throlting 1AFOt3A SCG 1A ISOL VLV. to aIjust AFW fo- *o 75 gpnm In doing so he has operated 1AF013A TWO (2) times in the last 10 seconds The NSO S now limited to operating the valve 1I tirves in the ri. t 50 seconds to prevent (3)
(1) (2)
- a. 1 Overfeeding the 1A SG
- b. 3 Overheating the valve motor
- c. 4 Overfeeding the 1A SG d 1 _-. _ _ _ __
- d. 14 Overheating the valve motor lnswer b = Exam Level Cn L pplicabon Fcon 1 iA 19401G132 F J 2.1.32 Rovau 4 SROValue: i3s! SecIon: i PWG j Rp ri 9 jj SyEtMunEvo T de]
GENERI lAbility to explain and apply all system limits and precaubons ind, Per BwOP AF-5, starting duties for MOV-AF013(A-H) is a max of 5 times w/l a one minute period. Prevents overheating the valve motor from excessive starting currents. (B) is only correct answer.
-
- Refrec Tid _ _ 3 71C i Reence Number 3eeec Secion2 Pag No. I 11 , Lo NmtrJ!
lNormal Ops- Motor Driven AFPSartup [wOPAF-5 --- 114 i -- - ----
I0106 ~~_
FInsoue f lFacdity Exam Bank --
11W_qefrzihc _1_ __
ju .UcnMiodlflcati-Mtod:
IFJ
.__ _-;I
___ 111 _
Sgn4cantfy Modified f ~
I rng_6eD
.1
- wUoWn Sourc Comme
_cmntYi _omn
._ _ _ -J K3 I ----- ----- --
-- -- ---- I--
L~---
__o - - iiit -JFeclmpty NRCl lO
RO SkvScr e SRO Skyiscraper RO SistemlEvolution List I SRO SystesnEvolution List I Outilne Changes Question Topic Generic Li --- jI The following conditions exist on Unit 1folio.%rj a refueling outage
- RCS temperature is 120'F
- RCS pressure is 50 psig
- All reactor vessel head closure bolts are t. y tensioned
- Preparations are being made to enter 1B..GP 100-1. "Plant Heatup'
- The following RCS chemistry sample taker- hour ago has been handed to you for your review Disolved Oxygen = 180 ppb Chloride = 160 ppb Fluoride = 130 ppb (1 is/are outside allowable val..e s) for current plaiil conditions and must be corrected to ensure (2)
- b. Chloride AND Fluoride Specific activity is minimized C.] Fuoride AND Oxygen Specific activity is minimized -l
_ __ _ _ _ _-_ ___ _- _ _--- - _ - - -- _ = _ _ _ __ _ _ _- -- _ = = ~ - -_- =- -- -__ _
__ _ _ =*-- _---_--- - _-- _*- _ -
_ __ __ = _ _-. _ __ J
- d. ONLY Chlonde Structural integnty of the RCS 3J d a Level JS s ljFclltyJ L M emory _ l jCcg 1Braidwood J x 7/19j]
i 194001IG134 2.1.34 ROVa l23 SRoVaue 9 1PWGJ ROGroup:4 [ j R r j
_ ___ _ _ -__ _ l_ _ ___ l[GENERi Ability to maintain primary and secondary plant chemistry within allowable limits.
Expanatlon of (A) Incorrect - 02 has no limit in mode IB t F uride is within allowable limits (<15 Sppb) (C) Incorrect- both 02 and Fluoride are within limits (D) Correct - Chloride iSOut of limits - >150 ppb. Also. TS basis is for RCS integrity, not RCS activity
,I -V-~ -- C, _ ____
Xi JE W~tyRetlrnowtum1 etecscbwaeN~Re~ .u b~
TRM - RCS Chemistry - llTech Requirements Manual j13 4.b 3 4b-4 1 Reactor Coolant LP j l1-RC-XL-01 j iii.A ____ 35 1 l 3 1
fT Basis (old) - = TS '=='= =_ JFAs= asA92_ = j 3/4 4-5 l Material Required fbr Eamm- inellon I -- I W 1Faciiity rt Exam Bank2_jIj5l fldUOOM11hod: SignificantlyModified Ud Dturlning tinn P
_ SOestlio B RCI -l --
Cormitent
_ Type__ Fdonmmnt___ . __ ____ _______
- -Compe-l- _ -__
R-__ ' !_
-TSand
-SRO Basis knowledge question Peer I-- .. a..t.lo
[ . .. . _.y Facility NRC I I
Question Topic Generic The following conditions exist on tUnit 1
- A reactor starnup is in progress tollowving an inadverta it vlarit trip
- The crew is performing steps of 1BwGP 100-2. -Reactor Startup
- All control AND shutdown banks have been fully withdra.vn
- The reactor s NOT critical Which of the to lowing describes the required operator action'
- a. Manual!l reinsert ALL Control and Shutdown Bank rods
- c. Manual / reinsert ONLY the Corntrol Bank rods
- d. Immed ately open the Reactor Trip Breakers Answer F la i Exam Level FR Cognitvevel IApplication JFcIlty: l
@1 . 7B19-0r1
-Facility Lve __ jBraidwood ~ .Ot:V71,2 L'¶A I go4001G01_o J22.1 ROValue:l I 371 SROVaue:. l361 ISectn:f. lPWG [R Group.] 1JSROGroup: _J i teIEvolutionTlitlj e GENERI L(A Staftmnt:_
IAbility to perform pre-startup procedures for the facility. including operating those controls associated with plant equipment that l could affect reactwity.
lifof IPer Attachment B,Contingency for not achieving criticality with all control rods fully withdrawn. Correct response is (A). (B) is action
__ 's- - 1for criticality below Lo-2 RIL (C) Incorrect because ALL rods must be inserted. (D) Incorrect - only applies to halted startups during R-efrence Title R I Facilty Reference Nunber R cSection_ Li.eNo. Rvislon. [LO. Nurbirj rfeactor stanup procedures B Attach B 1 --
- -=-- -- - --- = . _
Mteria Ra~dred 'tor Exaimination
=.~e~s =_ _- _. ____ _:_ __ _ __ _ __. _____J uet Source New - j Qestion Modl0flcfaton Method: r__ jUsu Dtirng Trmnkv roara I"Stion Sourc Comme T !onmnt __om_ _nt SuervisorCyom P
_R l r-- ------- - - - ---
- -~ _=- __ -= _-_- - - -- _- ___ _ ._
_Fcilty I NRC:
Ill-
RO SkvScrt l SRO Skvscraew I RO SystemlEvohition List I SiR0 gnbdEton LIst Outline Changes iNjav 1 2611
___j Question Topic Generic All of the following are the SAME for Unit 1 and Unit 2 during Cycle 10 operations EXCEPT:
iI
- a. Snutaown Margin Limit tor Modes 1.2.3 and 4 b.I DNBR - Reactor Coolant System minimum total flowrate C. Feedwater pressure differential pressure program
- d. Control bank insertion limits vs. % Rated Thermal Power j
_twer jc j Exmumeve ij Wo9nitiveLevl ] lMemory J F_<] 3raiwo E ImD-t: r_7/19/02l l194001G203 .22.3 ROValue:l 31 J leb PWG jSROVahJ IY Li IOGmup- lROR [
VO" M F _ _ l GENERI (multi-unit) Knowledge of the design, procedural. and operational differences between units.
o (A) incorrect SDM both 1.3% (B) Incorrect U-1&2 =380,900 (C)Correct U-1=85-215psid, U-2=80-220psid (D) Incorrect per C-LR figure 2.5.1 r iR & U-2 XTRMCQLRU-1 FCoI.R [S17 1i Power Ascension GP iBwGP 100-3 l100-3A9 l3.2
__b o ~uI I _ '__ .
. wouC ens 1 smilar to 2001 DC Cook sn#t7- V~_ _ _ I Ak--"!-!!"-O t
Y-I NRC 113
Question Topic Genefic Both Braidwood units undergo plant heatup and startups from cold shutdown condions Concerning the operation of FW009A-0. Main Feedwater Isolation Valves they are opened earlier in the startup process on _ (11 and must have startup purge logics satisifed before operating by opening bypass isolation flow control valves FW043A-D annd FW046A-D on (21 "i) (21
- a. Unit 1 Unit 2
- b. Unit 1 Unit 1 I
C. Unit 2 Unit 2
- d. Unit 2 Unit 1 lnsr a 'Exam Level R J Cognitive Lvewl [Memory_ j-Facility I raidood a t __ 7t19/O2J KA 194001G204 9 222.4 RO VaIlui.. 28-SC
- SO ---------
'R ale 1 eto ~ P G 0j j R Group:;[j
__ = = _ ____ _GENERI (multi-unit) Ability to explain the variations in control board layouts. systems instrumentation and procedural actions between units I at a facility.
~~hs~n of(A) Correct - opened on Unit 1 at -200'F in GP 100-1. On Unit 2 opened at NOP/NOT in GP 100-3. Unit 2 still maintains bypass purge permissive ckts (A) is only correct answer. 11
[-- ; efe ence Ttleb 1vi FacilityRefernnceN-be -- }Refel n. Section [O.
PlantHeatup Procedure rW1B9 P100-1 F .39j , J 7 __ ---- J lPowe Ascension ___=__=_=_ _ _ __ 2BwGP
-__ 100-3
_ - -14_ .0_ _=__ _ 1121P 21 ___
__ . _.__1________!____
I J_ _i I _ ___
sI Roqilred fo Examiatio e uirii7e7 N.ew QueiodoatloniMethod. ding Program
{Coment Type Ccmmenl llitviw vCo~n~ple
--- -g- ---
-- I J upervilaory1
= =- -L iFacility
! NRCI u4
Question Topic Gieneric Greater than 11 feet of vater Must be maintained over the top of the reactor pressure vessel flange durirns rniovernent of irradiated fuel assemntles within containment in order to (2)
I11(2)
- a. 23 Have sufficient wa er depth available to remove 99° of the assumed 10% iodine gap a-ivity relea-ed fronr the rupture of ar irradiated fuel assembly
- b. 2) Provide sufficient ..ater volume to allo. tinme for the operator to recognize the indcations of a dilution accident before Keff
- an exceed 95 delta K/K
- c. 23 Maintain sufficient water volume as a heat sink for core cooling in the event the operating RH loop fails to provide long term decay heat removal.t
- d. 20 Maintain sufficient water above the top of the fuel assemblies to ensure
-tattne radiation levels at the operating elevation tor tuel nanal-ng - - - __ - -
equipment remains below 4 mrthr Answer la I I _ExanLev
__ Cogniuve Level IMemory - J Fisdllty. Braidwood I ExamDat,: 7/19/02
_FL ___ - - .- - - -
r____
- L _
CA:j 1194001G225 j 2225 ROValue: 2. SRO Vall 5 71 FPWG ROGroup:
____IR G ystmEvi tion T
. _________I______ roup:
__ Di I GENERI K.A Stat man Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.
na Of (A Correct per TRM 3.9.e and TS (old) basis for minimum contained water depth during movement of fuel in containment.
___ _ __ _________ _ - _____ _ _*_ ___
Re d Tit Farility Reerenc Numrer e l Section Fa y---tfrv - - -- No.
_- aPge *RevIlonJ
--" 'LO. Number r--.
_ - . _ __ _ _ 3.9.e-_I _ __
iFH LP j Oh 52 J J __ jl77_
TS3/49 10(old) S Basis (old)
F[ Basis j 9-3 FAe66 LftbrblaReurd for Examinetinn i _
-S csten
- I pFacility Exam Bank JMtk&on odmceuon ehod: ffDirect From Source _Drd ing Trainj 4Clihn Sour mi _] 1998 Salem NRC Cornment Type 1 Conment- Reviews Complee j 7 - . _ _ _ __ _ __ __
Ir . _ _ _ __ _ _ Supervisory Facility NRC (1*
ROScfa l SRO WsckSraw l RO SystemEvolufdIon List l SROSn n tl OuUineChanges Question Topic Generic
.Li---'W ,
The following conditions exist on Unit 1
- Reactor was tripped from 2 power during a normal coastdown for refueling
- 7122/02 0900 Entered Mode 3. HOT STANDBY
- - 7/22/02 1300 Entered Mode 4. HOT SHUTDOWN
- 7/23102 0600 Entered Mode 5. COLD SHUTDOWN
- 7/23/02 2300 Entered Mode 6. REFUELING Tthe earliest that fuel movement in the reactor vessel is allowed will be _ 1) to ensure that (2)
- a. 7Q2502 1100 Short lived fission products have decayed
- b. 7;25.02 1100 Decay heat removal ability is adequate C. 7/26/02 1300 Short lived fission products have decayed l . 7126/02 1300 Decay heat removal ability is adequate IC i a ImLOv0e I 4.gnimve Level Appnication _j F lty Biwo2d W l194001G228 J 22.28 RO Value: 2 Vaue: PWG IROO Up] L l [1 E d 7_
lGENERI IKnowledrip rf n~iw arwi cn*t f...1 TR 39.a calls for 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> subcritbcal before fuel movements can begin. (7/22/02
@0900 + 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> (3 days. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) =
7/26/02 @ 1300 TS Basis (old) defines the basis as ensunng the short lived fission products have decayed off for radioactivity Eli ~ernmm ~] - - ~ne Seflo_] ijl F- - Nr~
Tech Requirements Manual _TRM 3.9.a - l a-1 I 17 Tech Specs (old) jBasis 3t4 9.3 9-1 A56 UFSAR _ li_ 15.77 J m ml IFd Em nal_ _ _ __ _
Other Fac SignificantlyModified _ 1 00 Wn ',2001 Prairie Island NRC 2000 Kewaunee NRC CommenType Cmet-____
nt j---Co
. j FaRility,
Question Topic (Gernr (
Unit 2 is being refueled tollowing a complete core oifload in accordance with the Core Loading Pattern supplied by Nuclear FLel Services Any deviation from the specified order of the PWR Nuclear Component Transfer List (NCTL). while transporting fuel to or from the Spent Fuel Pool or the New Fuel Storage Vault, requires tne approval of (1) AND (2) before any further action is taken (1) (2)
- a. System Engineering Supervisor Station Nuclear kMa erials Custodian
- b. Qualified Nudear Engineer Fuel Handling Supervisor
- c. System Engineering Supervisor Fuel Handling Supervisor
- d. Qualified Nuclear Engineer Station Nuclear Materials Custodian Answer j m=_
S p Cogntiv. Leve
_ =
v
_=.
Memory J Facilty FBraidwood J ExMmDat ___7/190 KA:J l194 31 2l2.231 RO,_ 2Ct1 SRO : ' n 1 O Group: SRO Group:
SystemlEvolutionTltfo I - .i
-le -
I._
-- - GENERI
_ _._ _._ _ _ . __-I-KAS ement __ _ _ _ ___
Knowledge of procedures and limitabons involved in inibal core loading.
of Per BwAP 370-3 (A) Only correct response. (BCD) Incorrect - all combinations of allowable reviewers for actions that do not
.. change the intent of the procedures.
Rmfdwhlf117]W R
'hiKi] S ctb:n Page N. Wuor J Administrative control during refueling JwAP 370 3 lb l__
C1OJI6 1.2 1J I l= __ -- JI ___ _-~- _ _ J __J1,
_- _ _1 771 _ __ _ ____T
,R Ruired for Examination JI I New, -odllcaten M.hod:U
_d Owing Tralkiin mm]
,QustionSourc Comments l
_ ___ r __ ___ . _-
CommentType] JComment j- ReVlCOn r --. _ __=-~_ ~ _-- =- _ ._
SRO J Fuel Handling procedures PO_
!- J lI Supericy
!_ _ _ Ji_ __- _ __ _ __ aclity NRC (11
Question Topic (eneric The following conditions exist on Unit '
- Reactor power is 75%. steady state equilibrium Xenon
- All controlling systems are operatir, in Automatic
- Turbine Impulse pressure transmitter PT-505 fails to ifts 50' value Control rods will respond by immediatel, slepping (1) at !2) steps per minute (1) (2)
- a. IN 72
- b. OUT 12
- c. OUT 8
- d. IN 8 Answer J 'ExamMaLevel B Cognitive Level Examate _ 71__
'Apph - - - Facily aidwood
_______ __ __- _/1_/
- F1940G233 Tlt.
- 2 2.33 RO Value:c 2
-nL SROValue:j 1 9I2 on PWG ROGroup3f ] SROGkoup: l i j GENERI
_ . _f nw_ . , _ co .e programming. . _ .
Knowledge of control rod programming I EI lntino (A) Correct - Tave program is 557'F-586'F or a delta of 291F. At 75% tave is (.75X29)+557=578,7'5F. Tref at 50% value is lItpb- (.5X29)+(557)=571 5°F. A 7.25°F mismatch exists. Rods will step in at 72 steps/min with anything greater than a 5 F mismatch if IJ I G *O C. __ ___ -
F __fRetice ritle- Facilile 6ince Number _ =I Setion, bNwuberj Pge Rn No.
Bwd Big Notes lRD- Speed & Direction j _ _ i13_
j~w r-- Note _ ~=--
_--_:---- ~_~_.:_ -- --: - -----r_J I -. -- - -- ----- - -r _----- ii -
tlRdRqulemd fo Examination 'I-5~Source~ Facility~ Exam Bank____ Qwe tioM lion mewod: JSignificantly Modified jbeed Dtan anigPrga Komment Type' Soure Comments Comment i,
j l___ R_ evIbwsComjI1 Pe j
_ 1 I
____ -j ,_ ___ _ _ _ __supervisy_
,-: -- - -=_ _ -- --- -=- = -. _ __
,, I I j :Paulty~w
- - -= = _ ..-- _ = _ .-- = _ --.
-L I'Fcilty
! e NRC
Question Topic (erleic Todays date is November 12 2002 -th (,uarter) You have been assigned to aithorize a rad worker to perform a routine task inthe Auxilary Building for .which an estimated dcse of 450 mrem will be received Each has an exposure history this year as follows A Age46 Cumulated TEDE dose of 600 rmrenr Has a high lifetime exposure re. ord B Age 38 Cumulated TEDE dose ot 418ri-ern Has 2 quarters with an absent z-c-ose record C Age 25 Cumulated TEDE dcose of 1260 mirem Cumulated SDE dose of 6 Rem *o the left hand D Age 17 Cumulated TEDE dose of 80 r1remn Cumulated SDE dose of 15 nirern to the upper fore armr Which of the above operators can be assigned the task v;ithout exceeding any of Exelon's radiation exposure limits or submitting approval for exposure limit extensions?
i!]IWorkerAA rb.1 Worker B -
!j Wo _eC _ _ _ _ __ .____ _ _____________
C.Worker Cl dJ WorkerD -
Ajbr ic tsam LWSI [S COgnh ieLev l !ApplicJjaifon I Braidwood 7/19/02l KA 1194001G301 J2.3.1 -ROV&lue:l 261 ~R ': [ US ] PWG RO u ] R j Syst*"nEvolutlon Ttlte l _ _ _ =_ -___- - GENER!
CA Statement: __
_ [Knowldgeof1CFR l_ 20 and related facility radiabon control requirementsI Explantion o°f (A) Incorrect - High lifetime exposure record limits this worker to an annual dose of 1000 mrem. (B) Incorrect - allowed dose is As decreased by 1250 mrem for EACH absent/no dose record on file. (C) total dose received would remain below the 2000 mremr
_%J. Sobv ,t. _vJ ***S v*J Sv ;a 03 Si; Jvcc CAiCCSJCl. *V's \Uj S Iv j S llvw- I C5 0li ;;;C'S .JJS vvv C Sllcl 555 uc 'C4 .C
___ Refmn~cTklt
-Ti
~1JLn3-IL F!#cy Rike umber
=_No 1 ;Reftrer S ction j]CPgNO. 1
.i evon4O el _1 .
Numbi]
.w._ _.r FExposure Control and Authozation Auhnain ___ RP AA--203
_______ -4 - I- ll2-5 2, j '2_jI _
'NGET __ ___l Student Study Guide Rad Protection -
I F-i .
Question Souroo: New jQuestion Modificailon Method. r : - ur m Question Source Comments Comment Type Comment RevIews Complete Peer Supervisory Facility NRC I1q
Question Topic Gerefc Which of the following is an SRO responsit)liity'
- a. Placing the placard 'Gas Decao Tank Release In Progress' on OPM02J ritor to commencing a release
- b. Performing second veriticationi of the lineut to transfer a blowdown tank to the condensate storage tank c.. Determining the release rate for a gas dec3y lank release
- d. Performing independent venfication of the lineup to place a release tank on recirculation j ExamLmIJ CoAnniriv Meory Braidwood _j amDat:, - 7/19/021!
194001G303
[KA: 2.33 ROValtiR 8;IVaFiU. I Sectbn P -< fROGroup:] *1 *O r*
pItenElliutibtlsf V _ .. ~1
__ = = =--- = = J- GENERI Knowledge of SRO responsibilities for auxiliary systems that are outside the control room (e.g., waste disposal and handling systems). ________________________________
A. Correct per reference. (B) Incorrect - second verifier is not required to be an SRO (C) Incorrect- Rad Protection determines a t_:: 1j release rate (D) Incorrect - IV is not required to be done by an SRO 9-~-~R(frcT----l Fael tdity t noe Amber S ctbn Fiag< [ Re. uftllL rt lWaste Gas Decay Tank Release Form .IBwOPGW-50OT1 El - j16 J -12
_ __ _ __ ________ ___,_:_=_ _ _______ __.__~~~~_
__ I___ __ *____ _
__ ________ ______ ___ .___ _ _2_ ____J-Ii -<r 1 _ 1 R_.dfor _wid - __ _ _ ____ _
=_=_ -i_ J Facility Exam Bank J Quetio mo umon Mwtod:-l Editonally Modified Usd During Training Poi3ramj
°onoum cmn~ats [20o1 Bwd NRC - - --
. Type .. - -- -o. -- - L m po.t - ,
= ____________________
__=______ _____.________________________
__ - -- =- _______--- ___________ - -=Sup"visory
_ _ _Facility NRC
ROSvcaRO Skyscraper RO SystenEVolkaton List SRO SillstarriEvohlution ListI Outline Chan~eis Question Topic Generic A Si-te Area Emerge cy has been declared at Braidwood Station due to a LOCA outside containme t The LOCA is into the Auxiliary Building. a direct pathwvay to the environment exists, and limited makeup to the RWST is available An operator has volunteered to enter the Aux Building to tocatty isolate the teak This action would significantly reduce offsite dose and has all required approvals from the TSC The operator has a lifetime exposeure ot 3200 mrem TIEDE and an exposure for the cirrerit year of 230 mnrem What is the maximumn exposure this operator may receive while performing actions to isolate this teak?
- a. 5 Rem TIEDE
C mLvlI rB ICognte Mee7~emory j Facilitl riwd ~ a~t:71/2 1'194001(G3G4 2.34 RO 2 ROaa: 3ej Slct1111on 31! ____G JROGrulp I SRO0 op ivol~on~lii]7 _ __ JGENERt Knowledge of radiation exposure timits and contamination control. inctuding permissible levels in excess of those authorized.
nitln fi er EP-M1713. Personnel Protective Actions - 25 Rem TIEDE is the emergency exposure timit. ITshatl be voluntary and limited to i
-mm once in a lifetime. (C) is correct i
[j7 Referenite Titl __ FacNftyRefeoteW Numner efrence Section IaIkp No. LR_*vb_1on] Uci9N~ed~ ]
PersonneljProt113 Actions 13 -e 4.1J 3 2 Ex o ue C nrol and Authorization- . _ ._ jRP-AA-20-3 _ _ _ _ _ 4___1 _ _ __ _ _ __77 JF
~toSourcio I'Facility Exam Bank I ~ oll~~ito:JTnfcni oified j~~~r~lgProgramj VA5ien Scums omet 2001lPrairie Island NRC __
- -- ipeer]
NRC
Question Topic Generic Unit 1 is in Mode 4 Cont.Li ment Purge is in progress using the Mini-purge Supply .nd Exhaust Fans While the purge is in progress 1RE-PRO01 Containment Purge Effluent Rad monitor, exceeds the ALERT setpoint Which of the following must be performed r'
- a. MANUALLY stop the containment purge in progress
- b. VERIFY containment purge AUTOMATICALLY stops
- d. MANUALLY align Post LOCA Purge filter unit
_~~~oniieee . _ _ ___ _ ____
Answer i ra J Exam Lavel B I erory eCognitive j Facliy: Braidwood xaDate: 71 /
194001G309 1., 239 ROValue: 25 SRO ale: 9]
_~- ~S~ IPWG PWG-I-I Group: r SRO Group:]-J L5 t/m/Evolution Title - GENERI i ii:
rowledge of the process for performing a containment purge. - --
r- --- - -- ___
illn ACorrect B. Incorrect. The ARO11/12 auto isolates the purge path not 1RE-PROOI. C. Incorrect. There is no auto alignment of pge filter unit. D. Incorrect. Procedure reference directs stopping purge (vice manually aligning the fitter unit)
R -l-b_ = F Facility ftqerc NFmber ] jo [ i ]
Cnmt Mini-Purge System Operation I IBwOP V-6 E.5 2 j l12 ___
Cnmt Vent LP JlI1 -VP-XL-01 _ I lI I _ ji9 P"I Ioqired hr Exanination ___j==__
lFaality Exam Bank __ ModfllMh: Direct From Source Used ui Training Program]
§ i Sour Cemment. 2001 Bwd NRC _
dometintType Conimmnt [-_rvis Complete
_rz
- L F ___ __,71 ___ _ _ _ ______ I lP~
________ __._ _ _ ._ _ _____ =__il _.sory
--- ---- _ __- - Facility NRC' IZJ
Question Topic C-eneric Given the following plant condltons
-Unit 1's at 100% power
- Unit 2 is at 100% power
-A confirmed High Alarm has been (letermined by Chemistry
-The 0 CC HX has been Subsequertly isolated The crew should now verify
- a. Only 11CC011 7 is closed and enter the LCO for Unit 1 CCVI
- b. Only 2CCO 17 is closed and enter the LCO for Unit 2 CCVV C. Both iCC0l 7 and 2CCO1 7 are closed and enter the LCO for both units for CC~%,
- d. Both 1CCO 17 and 2CCO 17 are closed and do not need to enter a LCO for either urnit-__
Ans---' Fc Exam Level I R Cognitive Level [6om~prehensioni Facility: [Elridwod xamate KA: 40131__21 RO Valu: ~2 7I ~SRO Value: 1 _3.21 'Section:~ PWG RO:oup 71 SRO1broup:iFj SystemillEvolutionTitle - _ _____ GNR Ability to control radiation reteases.__ _ _ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
00woionof IBoth vent vatves receive a closure signal from the common CC heat exchanger rad monitor. Must enter LCO for both units C ,Reuriancia- FcliyRfeeceNmer]ReeeceScto FP*u No:] IcOifurvill Tech Specs ... 37.7_ ___jCondition A F3.77-ljJ _
CC HX OUTLET UNITO 0 iBwARl1-OPR09J I__ ll 1 1 CC System LP j~~CC-XL-01 11--- __ _ Y~ 0_ _
Maltai-a Required for Exomination II Faiciil]ity Exam Bak i~onModifcto etoj iet Fro-m Soresldun rintingProgram Qusition Source Comnsi6200 Bwd NRC Exam Le entType Comet -Reiw Coplt orn
'7 I Facility NRCI its~
Question Topic (rIwer-.-
Which of the fcIcing condcjtions would NOT require immediate entry into 1BwE P-0 Reactor Trip or Safety lnjection' if the conc 'ion were to occur inadvertently aw the reactor operating at 100% power?
- a. Safety ln:eclion actuaton on Train A
- b. Different-al overcurrent on Bus 157
- c. Containment Phase A Isolation on both Trains
- d. Loss of Instrument Bus 112 with PR Instrument N-44 failed lExam Leel [R Cognitive Leval _Appcation J Facility:] Braidood __Examiat: 7/19/021
- ] [1i40 16404 1;2.4.4 ROVaIue j [f SROalue. r 43 SctIon:3 jPWG I O~oupj rj SROGroupi [j r-tu--Evolut-on Title1 - -- -------- _ _ _ __ _
Stement:
Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
of !I(A) Incorrect - Rx would trip entry into E-O is required (B) Incorrect - Rx would trip (loss of 2 RCS loops), entry inb E-O is required
- (C)Correct- no Rx trip occurs, enter and perform 1BwOA PRI-13. Recovery from Inadvertant Phase A Containment Isolation (D)
I _ - - . . S. _ _ . ,
r l # Referencel
- L FacIty Number - Re s;N.n L.O.Numbr
.InadvertanthAse Isolabon JAIOPRH-13 hlB I I- _ _ J Reactor Trip or Safety Injection 1BEP-0 B
__ __ _ __ - _ ____8 _______ __ _ i _ __i __i 1kat Required for Examination t Sor j Oethod: Used Duing Training Program LUatdnt Source Comments i 2001 DC Cook NRC J
-L{ ment Type Comment _ -- ___ iRvvbComplete
___ _ __=__ _ ___-_ __ I p _
. ._ __ _
- uIsory Facility NRC
Question Topic (Gr--lf'I :
1BwEP-3 Steam Generator Tube Rupture' instructs the operators to maintain teedlater flow to the ruptured stearm generator until narrow range level is greater than 10'/o This minimum level requirement elsures which of the following?
- a. Sufficient heat sink is available for Reactor Coolant System cooldown
- b. Thie ruptured steam generator tubes are covered to promote thermal stratification
- c. The ruptured steam genera or does NOT become a hot-dry steam generator 7 d.! Radioactive steam does NOT contaminate the main steamilines
_ _ _ __ ___ _ _ ___ _ _ __ _ _ _ Da _ . . . _~
l er l EV.IAf~j IComprehensin J 'Facility:] [Braidwood __J j[Exam l ;/191 246494001G406 ROV:11:- 3' ISRO_ Iae:j 4.0j S ction: jIPWGJ R6 roup:] jJ SfROG mp:1 [I SyteiilEvoluiuontme l l _ J GENERI
~KA Stetem.
Knowledge symptom based EOP mitbgatbon strategies.
onad1 EP-3 background documents - (B) Correct. Prevents ruptured SG depressurization during upcoming RCS cooldown steps. (A)
Incorrect - the ruputed SG will not be used for cooldown unless it is the only intact SG.. (C) Incorrect - No in E-3 mitigation with
.. flJ *
- i Vt~S fll lt UVLCWXtI ni ZC*.JJt l t .Vtt *CJlOtilU V; 3tC ttW@C Z1\;; ; J .. ;;.tot.tGai.6 O** CtGVUE
@tCOl;1:>OOVJW@0 -. _ -I 0, ttO ZIete reto c 1 u - aiiyRfrneNme eeec J~ FTitb [Fein J.
FIif~w RfNt eRofjn]p o
.Steam Generator Tube Rupture J Bw!EP-3 I__ _
_ _ .. =___ Step 4 ,18 __ _ _
.__=_
J Background Documents JjEP-3 _____ 62__
11___ _ __i_ ____J -
J_ jl_____6 - _J__
. 7 Zi __ __ KZ Q _
{- ,
~______- ~ ~
acece ty ModificationMetod:_ fDirect From Source Ue uk Quetion Soin <Facility Examn Bank J uFtonl~dlnl tho 4V_ UeedudnranhPrngam QUetion Some Commentb I~_
.Comment Type jvw~oet bLul _ -_ __ ._ _f i _Peer ___ _____ ___
___ [
! ________ __ _ _ 'Supeviecry
.r 7 Facility NRC It*-
Question Topic ,ef.ri The following conditions eis! on Unit 1
- Bus 141 is DE-ENERGIZED
- Bus 142 is DE-ENERGIZED
- RCS pressure is 2220 psrg and decreasing slowly
- Pzr level is 31I, and decreasing slowly
- Preparations are being made to cool the RCS to 350'F in order to minrmize 'urther RCS inventory loss Operators are performing steps in (1) and are CAUTIONED NOT to decrease RCS Hot Leg temperatures below 350 F to prevent (2)
(1) 12)
- a. 1BwCA-0 0 Loss of A I AC Accumulator Nitrogen injection
- b. 1BwEP-C Reactor Trip or SI Pressurized Thermal Shock Condition-s IC. 1BwEP-0 Reactor Trip or Si Accumulator Nitrogen injection 1BwCA-0 0 Loss of All AC Pressurized Thermal Shock Condibons
__ E m .i o nii_,_-
h ' 1 Comprehension I Fac-. 1 rBaidwood _l E_ 1 _2 1194001G407 _ 12417 'R11V6.R -- 311 ISROValueW r3F8 sction:] PWG1 j _j_
-- ou__ Gr.: _
1j ' 1l -W- u_38 GENERI Knowledge of event based EOP mitigation strategies. ___
~f Correct - ESF Buses de-energized requires use of CA-0.0. During the cooldown lo 350-F the operators are cautioned -To IPAl() ~
~~
prevent injechon of accumulator N2 into the RCS. hot leg temps should not be decreased to less than 350°F (B) Incorrect - EP-0 (ACorr wect vcE Buse dcs-engze require usevofcC-.O Duringa te coldw v~ the. opwwerators arewc;-*
steps are in progress (D) Incorrect - PTS is not a concern (per background documents) Cold leg temps will be monitored for pts cautioned vl;v;c"T 11 R-efr -- t t- - ai Rf nce Nutmber Reference~lScltion -] Pag.No7] Rvhbn; L.0. Number rLos-sofAll ACLP -_ ___- jlll-CA-XL-01 - - i - I 7 -[4_
- i 6--
Loss of All AC Power J
[1BwCA-0.0 J3P j 9 [Thj 1 .r-_---
[Emergency Response Guidelines ERG CA-0.0 step 16 IJ - jJ l18 1C J1-f Reuired t for Examination i _ _ _I won ource: Facility ExamBank l uelton Modifcto Method: l Significantly Modified P oJd During Tra1iing SourceComments] 20Bwd NRC
- 1 Llomm"enType Comment - - 31 views Complete r -_ - - - -_-_-- --- -- _------ --- . -.-- ._
I .. .. . . . . Supervisory1 Facility NRC
Question Topic (,r iee c An emergency call has been received by the Assist NSO in the control room. reportirg a large fire in the Turbine Building Which of Ihe following is NOT one of the Shift Managers responsibilities while completing the checklist for a Fire Hazmat Spill Response'
- a. Verify the Fire Brigade has been notifieddispatched
- b. Notification of Rad Protection to dispatch personnel to the area
- c. 'Assessment ot the fire.scenario and classification for the Emergency Plan
- d. Announcement ofthe fire over the plant PA system and sounding of the plant fire alarm
,.:_=: _ .___._.:____: : E :_m= _ :____, =_ __/.
Wivw r d ] ExamLevel I C tognilive Level Memory j Facility: Braidwood -l 7/19/0211 KA1 [194001G427 lue2 I 30! SROVaIuo:1_ jPWG ROorwP 'I SRO reepl iSctonll jSystenEvolutbon T__ _J GENERI St_: - _ _ _ _
I Knowledge of fire in the plant procedure.
l d (A-C) are all part of the checklist for the S Manager to perform. (D) Correct - this is the assist operators responsibility per the
_ lchecklist__ _ _ _ _ _
I R.eec _-T Fire/ Hazmat SpillResponse
_ __~sfyefecN B
BwAP1100-16
_efrec me
_clo ____
_ AppendixA&D j4,12 J 14_
_ _ __ , ___ _7-* _ _ JJ__ _____
R _da _srdo Exam_ n
_on__ . _ ___ __ . _ __ __ _ ___ _ -_
- _ I _
¢nowc:-[rw =__J laeUon~lodflicaon Meod: l " ,Trlh~
Quwtbn SonrceCommntne __@@
tmentTyp. iComment n Co n
- ---- --- --- - --- 7-- = 77 I~~_ ~ _ _ _ ________________________ __ ___.___ _ __ _ _
___-_-- -- - - --- i - --- ----- ---- --- ------------- --- ___________________________-
- - -- __I h_____
NRCj lZ1-
Question Topic G.encrc A large Break LOCA ronctirrer .:.ith a loss of containment integrity has been Ni TIALLY classified as a General Emergency The offsile state authorities wili Fe notified of this event on the H11 onorec and the NRC will be notified on the 12) phone I (1)
- a. Green Red
- --- I
- b. White ReC
- c. Red Gree-i
- - --_ _- _- - _-- -_ _ -- -. ~ -_ _ _ __--_ __ _ _.
- d. Green Wh e Lf Answer ja j IExam Level 'B Cognitive Leve [?emory 1J1Faci Bradwood _ M_ 7/t-7/1 KA:! [i94001G429 J24 29 ROValu: l 6 SROValue: -Ei n - - G SRO rp_
LSyfstmEvolutlon Titej I = = = J GENERI Knowledge of the emergency plan. ____---_____---
IlExlon ot lA)Dedicated lnes in the MCR for NARs is GREEN and the NRC is RED.
'.Rerenc Ths - -- ] L FaiiyRfrneNne
- iiielowi 4s Pae o. Nu~
Nobficons ____ EP-AA- _ ___
jMCR equipment -- 77 -- _ -- r- -
_ zilzz- __ __-- -J--- 7LI____ I -: L-.V-_
~~ Requiled - for -.
xeaminati on Qitlon Source:o New ousuioni C_ Mo ton hodo: Used During Training Pm7 Question Source Comments Comment Typo Comment --- ___-j ,RevlewComplet F-- . -- ,_ __ _ _ _ __ pe,
_ _ _I Fa. ipity NRCI 128
Question Topic Genetic The Unit is iii Mode I Nhen a power supply problem in the Annunciator Cabinets results in a loss of most of the annunciators onl1PM01J. lPM05J~
and 1P%1O6J Maintenance estimates 1hour to repair This condition 1 an Emergency Plan EAL threshold and requires (2)- monitoring of plant status (ii (2)
S. meets Continuous
- b. meets Hourly C. dces NOT meet Continuous
- d. -does NOT meet Hourly alExmLevelTs~ 'Cagnltive4Leve I~emory jli* DW /110 1
100G3 2.4.32 RO au]I31SOaU.j9J[ei. RO W rup ISRO~ru twavuioTlmifi7e-1_ _______ GENERI
[Knowledge of operator response to loss of all annunciators.
~~iiii](A) Correct - per Bwd EALs - MU6 and 1BwOS AN-1A AAR A.3 (8,C,D) Incorrect -the event does warrant EP classification and does require continuous monitoring Rftitr~n.'lb: *. 7 Pc~~vu.Nm~Jj~ ~~iNo.] ~ ~ i~e~
ILossf AnunciatorsJ BO AN-1A [A.3 F21____]
BraidodAs__ _______JThreshold Value 54
- - _ _ j MU _ _ _ _ _ _ __ _ _ _ I FA I aor i Required for E m _ __ _ _ __ _ _ __ _ __ _ __ _ _ __ _ _ __ _ _
~~S~uome e __ - isinos~na: - uring Trainin Prgra J§onirln Source JCommlouaConM SRO _ Knowledge of EALs and Actions in the AAR (selecting correct procedure) L~
'NRCj I1c9