Text

Forwards Comments on Questions & Answers Associated w/900221 Exam.Recommends That Comments Be Considered in Written Exam & Serve as Basis for Refining Exam Answers
	ML20012C780
Person / Time
Site:	Cooper
Issue date:	02/23/1990
From:	Dutton J; NEBRASKA PUBLIC POWER DISTRICT
To:	Whittemore J; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20012C776	List: ML20012C775; ML20012C779; ML20012C780;
References
	NTD900070, NUDOCS 9003230207
	Download: ML20012C780 (72)
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.m COOPER NUCLEAR si ATION Nebraska Public Power District

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NTD900070 February 23,.1990.

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U.S. Nuclear Regulatory Commission i

611 Ryan Plaza Drive i

Suite 1000 Arlington, TX 76011 j

Attention:

Mr. John Whittemore l

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Subject:

. Comments - NRC Examination Administered February 21 through February 23, 1990

Dear Mr. Whittemore:

1 Attached please find our comment on a question and answer associated with the subject examination given on February 21, 1990. We believe that our comnient should be considered in the grading of the written exam and serve as a basis for refining the examination answer.

Please contact us if you would like to pursue our comments further or if additional clarification is desired.

/

W. Dutton-Train Manager JWD/dj s/ LETTERS 2 Attachments cc:

C.~A. Trevors w/ attachments C. R. llorn w/ attachments l

K. C. Walden w/ attachments R. Brungardt w/o attachments R, D. Creason w/o attachments l

K. K. Finn w/o attachments TS File' w/ attachments 9003230207 900316 3

FDR ADOCK 0500 8

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-1990- SRO LICENSING EXAM COMMENT

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I Comments-from tho' SRO NRC-Examination : Review performed on February 21,- 1990,-

The;following CNS. personnel were involved!in the.. review of-the exams:

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D.~ C..Mueller.

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Attachment 4

' QUESTION: 031-(1.00),

Which type of level instrumentation system is used to provide the signal which allows opening of the Torus Spray. Valve?

a.

Rosemount b.

.Barton c.-

Gemac d.

Yarway ANSWER:

031 (1.00)

"a."

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REFERENCE:

COR002-23, page 43 216000K405. 216000K405

..(KA's) k COMMENT:

Correct answer should be'"d.

Yarway" in accordance with attached references.

REFERENCES:

1.

GEK 34569B Section EA 1 Page 2-13 2.

Procedure 4.6.1 Rev 14 Attachment "D" Page 1 of 2 3.

Equipment Data File System (Print out attached) 4.

GE Print 791 E 261 Sheet. 4 and Sheet 8 1

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t U. S. NUCLEAR REGULATORY COMMISSION SENIOR REACTOR OPERATOR LICENSE. EXAMINATION REGION 4

FACILITY:

Cooper Station 7

REACTOR TYPE:

BWR-GE4 i

~DATE ADMINSTERED:

90/02/21 j

CANDIDATE:

i.I

-INSTRUCTIONS TO CANDIDATE:

Pxinte for each question'are indicated in parentheses after the question.

To -

j pass this examination, you must. achieve an overall grade of at least 80%.

l Examination papora will be picked up four and one' half (4 1/2) hours after l

.th -examination starte.

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. NUMBER j

TOTAL

-l CANDIDATE'S l

CANDIDATE'S l

i l-QUESTIONS l

. POINTS l

-POINTS l

OVERALL

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GRADE (%)

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All work done on thie examination la my own.

I have neither given nor received! aid.

L Candidate's Signature i

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f NRC RULES AND GUIDELINES FOR LICENSE EXAMINATIONS During'the administration of thie examination the following rulee apply:

-11 Chehting on the' examination means an automatic derial offyour application

.and could result in more severe penalties.

-2;'After the examination has been completed, you muet sign the statement on the cover eheet indicating that the work le your own and you have not

received or given aesiotance in completing the examination.

This must be l

odone after you' complete the examination.

-. 3 Restroom tripe are to be limited and only one candidate at a time may leave.

You must avoid all contacte with anyone outside the examination l

room to avoid even the appearance or poecibility of cheating.

4 Use black ink or dark pencil only to facilitate legible reproductione.

l Sk Print your name in the blank provided in the upper right-hand corner of g

the examination' cover cheet.

Sc -Fill in the'date on the cover sheet of the examination (if nececeary).

i 7

You may write your answere on the examination question page or on a

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oparate cheet of paper.

USE.ONLY THE PAPER PROVIDED AND DO NOT WRITE ON J

.THE BACK SIDE OF THE PAGE.

8e If you write your answere on the examination question page and you need more space t.o ancwer a specific question, use a separate cheet of the paper provided and insert it directly after the specific question.

~DO NOT WRITE ON THE BACK SIDE OF THE EXAMINATION QUESTION-PAGE.

9: Print your name in the upper right-hand corner of the first page of answer

heete whether you use the examination question pages or separate cheets of paper.

Initial each of the following answer pages.

10. Beforo-you turn in your examination, consecutively number each answer heet, including any additional pages inserted when writing your answere on the examination question page.

i 11; if you are using separate eheete, number each answer and ekip at least 3 lines between anewere to allow epace for-grading.

12> Write "Last Page" on the last anewer eheet.

1

. 13),UTe abbreviatione only -if they are commonly used in facility literature.

f Avoid using symbole auch as < or > eigne to avoid a simple transposition j-irror resulting in an incorrect answer.

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-} QUESTION:001 -(1.00)

$v JDuring:a'. fire,.the Fire Brigade Leader will act as on scene Incident.

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" QUESTION: 003.J(1.00)-

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t Method", an operability. review is conducted and'the component is found

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be 4 men-action is initiated to verify operability of redundant-j equipment.

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A 'c When all' reasonable attempts to perform the test are exhausted.

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'di At the completion of the operability review.

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J Page-7-

- QUESTION: 008

_1.00)

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Choose the correct item below concerning event data-archiving capability of the Plant (PMIS) Computer.

a.

.The capability for archiving is about 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of an event without operator. intervention.

b.

Once the ARCHIVE file is full, it is automatically backed up to tape.

c.

An event must be declared in order to save the ARCHIVE file to tape.

d.

An event 1cannot be cancelled until the ARCHIVE data file-has been

! saved to tape.

. QUESTION: 009 (1.00)

Which of the following is beyond the normally accepted responsibility of an individual worker, as it' pertains to the ALARA Program 7 a.

KNOWING and FOLLOWING the basic contento of the CNS ALARA Program, b.

REPORTING poor practices-to the ALARA Coordinator, c.

FILLING out-the Post-Job Review Questions on the ALARA checklist.

d.

SUGGESTING exposure saving ideas to the ALARA Coordinator.

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2 QUESTION:-010_ (2.00)

[.w Match one-(1) INITIATING EVENT in column "B" to each CATEGORY in column

.'"A",

in accordance with Attachment A of EPIP 5.7.1, EMERGENCY

CLASSIFICATION.

Accume UNUSUAL EVENT in all cases.

"A" "B"

CATEGORY INITIATING EVENT a.____ Radiological 1.

Losa of meteorological aeseeement capabilities b.-

Operations:

2.

Explosion within protected area-o.._

-Fincion Product Barrier Eloss' 3.

Failure of Safety or Relief Valve to close d.

. Power or Alarma 4.

Failure of Turbine rotor' causing ocram from full power 5.

Trenoportation offsite of injured contaminated man 6.

ECCS is actuated and water is injected to the RPV

QUESTA0N: 011' (1.00)

'CNS Procedure 0.2,. Station Organization and Responsibility, states that the LShift Supervisor is' responsible to a'seure safe etation operation.in accordance with certain documents.

Choose-the correct' set of documents.

La.

Operating License, Technical Specifications, approved operating procedures L b ~..

Technical Specificatione and approved operating procedures c.

Operating License and an NRC approved Emergency Plan

( d ',

Operating Licence, NRC approved Emergency Plan, and approved operating procedures.

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4

-QUESTION: 021.(1[00)

JThe following Turbine / Generator conditione exist:

o-Turbineile' latched.

o-

,One generator output breaker is closed.

.o'--

Bypass valves are partially closed.

- What le the OPERATlNG MODE of the Digital Electro-Hydraulic (DEH) Control b

' System?

la..

Turbine Start.

? urbine' Load Control.

1bh T

o'.

Turbine Follow Reactor Manual.

[d.

Reactor Start.

QUESTION:-.022 (1'00)-

-Concerning normal operation of the DEH eystem in MODE IV, choose the

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correct statement below:

s JeN Raleing the pressure control signal above the' load reference-will cause the bypass valves to open.

b.

,Roducing the valve position limiter setting to below the preenure control signal will cause an increase in reactor preesure.

c.

Reactor power is controlled by the operator adjusting the load reference signal.

.d.

. Governor < valvo control will automatically transfer to manual ~1f a loss

~

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Page 16.

p QU$STION: 027- (2.00)-

.. -Match one of the conditions or setpointa in column "B" to the SRM alarm or indication it will cause in. column "A".

Conditions or.setpointe may be used more than'once.

" Af' "B"

ALARM;/ INDICATION CONDITION /SETPOINT' a.-

Detector Retract Permit 1.

Function Switch not in OPERATE

,E

.UpacaleJALM/INOP

~

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3 CPS QUESTION:-028i'(1;00)

Concerning SRM. initiated rod blocks, choose the statement below which describes the interface with 1RMs which provides' bypass for rod blocks duri'ng startup.

.a..-

IRM channela provide a bypaso for SRM'INOP rod block on range 7.

b.

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c.

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d.

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4

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4 3

m.m r!e 6eir;ueversehffow y

m WbdRT (fhf gd hf> measuring?piocess;resb1 ting fro'm7a stopped 5RRipump 1

' ~ ~

'~g g

iforttotal flow; W~

f' s,

o,

.9 t

Mdo m, %m ; N.

> x weW@* j@eg -Thed. %reverselflowTresultingifrom al stopped?RR jumplia addedKtot"_

m N@5 m:

4 Me f -

'7 a

e

$q $i d m W -$ N % operatingfside#flontoimeasureFtotel" flow.

i '

W t

y

. m-

?

y

' ' ~^

m eg% ab 7-j s w, g@f

-r,

. < y p=-

I MW ; s%All c209etfPlumpid/p Emeasuring devices; util'izeian? identical; upper' ediffuseritap M

/

he m

w w="

x w.

e 4

w%fh 4%%

f -

wr e

e4 m

J.y%....$ v

%d

y C.n

?

+

a ae,

3, 7w y

,..<..,m'W'

.- My..,.

4 i,.

m

$m +y <

t

,m e-

'-i e

QUEST 10N:sO33

% @&g y m ' ;y %s;:(1100)',;

6%g a

.n

._v..

. ~

n.,

~v.

Q ConcerningbLPCI? initiation <andreactoridepressurization;:cLchoosethe,co,rrecti,'Ep y %titeme'ntibe16w y*

N

' ~

~

lMe 1

M&d# M i N

h N,M.o_h %.,h..ejeStable(checkWalveswillbeginto:opensaN298psige s

m

.N

? -.

??.A

' ~

1*

~~ k Y U

a.<,

u

+1 A

WN,#fAXsinglesloop Lief capablel of opumping i greater thanJ1510001GPM.

kmw a nn.

l i x.

.=

4 i

-y S AW 7 :,

@g W

. x mg

. y cM W& pThef minimum &flowJvalve; shute?at alsystem' flow 1ratielof t2300 GPMW 5

g' 4 t.m fm w+- s y "1. _. vw-i m.

x 4

m s

+

js qa w.d M OAn{ initiation l signal cadees(the RHR suppression:poolfsuction9tofopen.s a

~

+;,

w&r g

,+y w A. mpy

+w L-u.

4 s-e

-.c 4

i-tqwow o4,

A

~

p&gh> >m,,

,W

=

o-y.g 5

tc m-

-m egn e$ QUESTION DOS 46(1.00)T, ^,

m 4

n Am y " _~ ~ ' _%

^

y

-c w$4Wh'ichnitenRbelon

describes Thow tthe RHRL Puinpsiare2 loaded.on to theirt m.

.m...,

s.

m

/ p:Mm ; ~pn: -N M ipectii/eN. electrical busesfif:the startup. transformer is.not,available?

~

x SpMM WTheduinps wil10 beg'in1 sequencing onjtf 5 second intervale 10 sec'onds1 m

%QfkafterJpower91siavailable.

p$ImwuJM m m

. mm w ~

4%,N MTWR.pumpsLetart with n~o time delay and two-start in 10 seconds when" b M M power;;(is available?

4 y

e duv

~fi~-

3 4h

?,

3 M d $ $Two Sumpefstart1when power becomes available and the other two start 15:

w Mg6 ; e deeconds-later.;

pwn y;n,i a-qgdk;iTheipumpswillbeginsequencingonat5secondintervsleassoon~as i#yp.

+'powerdis.available.

$w

. w#WB w

w

+

t.

j

.ll 1

p lk ; -

1 h:

MW;, z __ _

b+y @% l'

'3' j

j:yyfli p %, j= ::f [

& yh dif WW ^

N

o 4

W %%;k ".

2 W hh ci

o Whh, yM.: /

u.. M

~ c u_;

q

.c 3 syy n

%endun1 nn. " - -.

1:,

A

- 3

-t

yngi swQ wm e y>r, g ys y+ &

k

r j'

'y t. :;f mwggg w

Wm, s,

m s. m

. q q ;; W - w s

4 3

i

= n,ac: 7

~ w%&w, Qg

-t m

4 1

h

^

>t

. i. W if gw

kp0 Y; YhknV?y rd N W r $nC l& k!

v

.N\\

Y l i ?"

s

'w

~

^ i.

> &?

~

L f 1.

M s,, ' ),, y". 2%F

p i

.*~

WB[Ejg$g WE t

g R

knM ' bh % r#

i eMM-Wif - p,' a.

z' m, Pd,. '

1 19 Zs&+

aR M gw m M.m = W~

+

e MW. ~ a.

s',*

m %~;

mh a..

$NSMh+-P Q@ flb W hi s", C &";\\ ', )l)

~Q'y :Y;v l

R

\\

6 E3 M

1

,)'.

+

a

' WQ,,,_

=-

f

s !/

ju? '

^ V,

,_s s

_ G;p lr W'

8 MQUESTIONO OSS% J(LOOF W

~

'M as, f W N j

. n v a,< a

-n s

0f$$$[p'; f.0119reactonscramfoccursMenMBOVACCpower to 'MCCJ-JL]isliintserruptedifor

~

Q>

"IU

~

t. 9 g2isecohd.sqjChooseetheffo116wingjitem;which 11s an. accurate assessmentkofi

~ fH r

G B thesoccurrence M.,E s+-

we} x y w~ j ' '

e.

,y _Q M_.f ? f' #Md The t acrasi7did inot) re sult sfrom - the Miose fo f; an i RPS f MGiset.g p

_,p a

,)

<m as.

,r

a

+

ir.

r m-c m

4._

w" Hg / * ; m_.n :

M b %, lLThejRPSTMG!performedJae it:was[ designed.;

g' '

c

@$ % l y I. Q. [ ; K

+

v n

qw n'm & ng;ThefRPS MG? performed ~asi:Atinormally does.:,

- Pj 1

s s

4,,

a

' sa vi r:y s q 4,,_

~,

.x g

M Nd f Q@ W;nterruption) '

half? group'IfandsIIAisolation resulted;.from.the RPS powery

%hd i

~

,((

.. e

,m -.;.

egws Mm,m u

m m.

f-MhW W D.

l e c,

' b;, s 3

' ' Mtl T

%g x

3W

'Y n A:;-y a;g

+

~

+.%.

kQUESTIONbO36i3$ODI, 5

~

bA;.wg a,w nw,,

%*u, 11for a Turbine. Control"Valv'e,n"

Mw

~

M M I6hYdflthelfo11owin'gcprov' ides;the?signE..

e 3;W;y CV)y? Fast fClo'auren Scram?.

' Jln J

W T

y n ; -

.q;;

@y y

4 n

4 y

m i.

ggi f RateW o.f., TCVs. positionichange.

m mr a

w m..

vmm s.

e A M C. JTurbineiconi:hol/ fluid pressure.

3

y t@e' A ;,,, s.

.c

s. _ T.y_

.q ct j

~

i

,_[

7 1

s R Ri$w. bTCVf,positionilimit switches;.

+

i W

ma pon u m 7;,

c...

1

.a c

i,gH.

k id? N. Power,vtorfastvecting/ solenoids.

3 g

g y y

yg ~

\\

bj

(

pj.

c,

,,y h.

k' g~

..o S QUESTION:. _.J 037f -_(1;00)s 2

m.

u j"(5 yM m

@Y@hM

,4 4.

.7-

.s.

Conc,,erning4the Reactor FeedwateriControl'systempchoose'the. correct # items

~

M1ow:E, s

~

L-

>d h re ' m n_, -. #<

w,>

nom

.m gj.g, 3.

~

w g.:j l M.ywy;

> G..q p"

4 < SReactorfFeed Pump-(RFP)Gspeed can be controlled by the Vesse'1: Level y EF P 1MasteriCon. troller,fthe1Lo.vejoyfController,=-or the'Startup Controller.

~,

u

~

I, i,1

..R.t

+.

~.

M W R S,,I6 Control Lovel "B" is$1ost~while-selected for control', switchingLto!

,$ $, *fContro19L'evel?"A"iwil1~NOT' clear the RFP lockouth

.e Uj

.h '

J 2.

4 r.,-

Q cl F1fRFeed' Flow "A": instrument ~is lost whilefat:50% power, the Lovejoy.

^

ME,M,y" Jc6ntro11e'rf wil1V automabically assume control of 'RFP lepeed.

~

y

$nmW

-^

i n

@i sde

. ~

N

'InbthesBALANCE position,- the Vessel-~ Level Master Controller-deviation by [

%ctual 1evel.

~

h Emster indicates the difference between the desired level and the.

w !,

H W3,.

l

-..(_yf

}

gy4 s

3 u s-L.:,,

4 fl 2 if Q r5 -

1 hkl Y

h. w* sg += m%._.

f M%%

w p e. \\ h (?

5 h

o a

s

mgy+m m a m m p w pg~ : a g~re w. w e+ m + e

y m a... ~

.m+

l1 3< n & Pm bi m., p y5y..m a nh w w wp m

w.w 1.qn e lS@[s ((i Y ~

9t,E

?~ + w s x__

w 3

, p;+ 3. >..t 4

w m;

w t

+ fiff,,a m1,=-

.--[.p, -. [__

'f"

' n-q 17$N A.M ~ / ' i

^

' %j+ c

' M^: '

f, W

e

. ;Q

%j c

I

's

.f &w ;ol+39+ m.

${f S f w

q"e =

AmW'

.t M d e @j/IJ i d;n m

o

_;y P ** r 20.9 2

..q%M ' g "fp_

N e gg yg 9-}3p _

[+

s I

fi

>g g

pgc ; m; g qu an u.m, a

~

,skw&wa:x.

. q--

n.c.

y

~

t

.n

,~

~p m v a~

lW_&&&:,n' '

, l 2

w m

w$

-4 '

a ~

QUESTI.ONn_038 W 2(00P

. s

~,~

m

,. +

. a..

.. &^

, h,L, s-;.

-v

?~

.x.

v i O'

-.,. - +... - .a We Matc.h. M,ineY(11)?. fun 6tioniin c'olumn TB"> to e,ach RodiBlock Monitor l('R. BM.P, u

m r

nyComponentio% circuit)inic'olumn "A".-

4, w

g

. e m ~~- as

+

w r

+

u

(!y mkj_

,.,e 4

.. =;

e"L J

~

, COLUMN:"B"J,

2,~7, E TM_ J WCOL,UMN: TNh

, i r

u rw' e

m

{

k_'

4 % g @db w MPONENT/ CIRCUITS RCO

~

4!

1 FUNCTION, s

z. m a

/

n nw@;;:m:g..a/ Count [ Circuit!

n, r l'-

Produces T a 'signali pr. opo. r..tional? top '.r w.

m.'

,y

@ML; m

1 i"

thermalipower;

- 9 r

V n.

MQW, 7

Select %Matrixk

+

yyQ,jg j.l'Avereging, Circ [uit-2.<

Adjudt? Gain ;of? Averaging ; Amplifier h Km h

3;

..l:

m e

%DA

~

+..i y.,idf:

i. Trip"Circuitt

~

=Ensuresihs1fJofTassigned1LPRMi'

?

' d; c,.,

imonitors are' operable.> #

s s

~

a,m w,

s y%4.

(

7

.g i

~

(Gends:LPRMLoutputs1todaverag'ing

_ 4; (y*j NN<

circu'itl- '

J

%~

,f ' :*

,)\\

,t

~

3[f' s

k g :@&n,.j%' ),H t W

_\\

J.

5.:

.n y

1 CProvides a trip si$nal~ewhen91nputi yt U HE l'

7 7

y% ;

' signal l passes referenc,e; point.1

,n u..

+; r g.,. a,_.

?h

l

.)

E W'

ril 4ai l

4, 3

L Q6F ' +

/

.r w~ '

T QUESTIONh 039} N 00:h'-

s

~

n;a a so.~...s v

M.mnChloosofthesitemibolow whichidescribee an,attributeiof^theLBackup? Scram;

*, u

~

r e.

b ivDves?

i

+

e m

g m%ngk M. Norm $1 $.xehobgTzedLandlwill de-energize [upon alRPS ScramEsigna I"d c

, we w.s e

~

dik ' 4Aligne.disdch t. hat 5.two. eval.ves 11no series.coneifrom.t each RP,Sc trip"

- s

v. p et %.y g >

>channelWmustractuatento-ventEtheLecramTair header.

ey-e

~

h-

's.'is=,,. f l -t 7 c.

MolkI7 I cDesigned$such that-both-'RPS channeisHmust. trip-in order for anyLone-b w M,, Wofitheivalves7t'oractuatey

~

7 ss, a,

LP. y

,$,[ :; -.3Od#:..

s 1-...

s.

.'.NormallyJpowered fromsthe1RPS Buses.A andLB.-

a

.~'

f8

-...M-

.-4 '.

w c;1.

Jt St+

. u.,

[

g. '(- l I

'a; I.

sm l

> ; p, &.,. 9 G p

M yyr

=<

y 3.4 )

%:D y0 k

hl.f l_

,l N.L,

iW%l-T*

3;^, m w

t

.u

(

gg))

w x

.~.-

l:

l gy

-y

~

f syy ' Mf.,

yS

a. m

- } D,. *.) n l -

,' f 'a '

5 f, y )

.g

~.n,, m, m.f d s

k' w:.h '

r a

f 5 s p

~+

O. h: )c. ;.VG y

{~

..;. w 2,.

(

m?yw. -5 1

,1

~

,f

dMN/i !..Cf,Db 4

~

iry

.Page 21.

~ QUESTION': 040-- '(2.00)-

~

Match one (1)' function in Column "B"

to each component in Column "A" which-provides that= function DURING A SCRAM.

"A" "B"

-COMPONENT SCRAM FUNCTION Ja.

Scram Inlet Valve 1.

Positions to, pressurize overpiston' area.

b.

HCU Directi, Cont. Valve 2.

Shute to preclude release.

c.

Backup ecram valves 3.

Does not Operate, d.

SDV Drain Valve-4.

Positione to pressurize underpiston v

area.

5.

Positions to vent scram air header.

6.

Throttlee to provide'etability.

_ UESTION: 041 (1.00)

Q The~ Reactor Manual Control System " EMERGENCY IN" mode of operation.will

NOT.bypace:

a.

Auxiliary timer and RSCS insert block.

sb.

RSCS incert block and RWM insert block.

c.-

RWM insert block and select block.

d.

Select block and RSCS insert block.

maa

$...,f.i

. Pag 22' o

p w l.

LQUESTION: 042- (l';00)

' !! Choose the. correct otatement below concerning R'od Worth Minimizer (RWM).

~

ch rectoristics.

l A select error will cause out of eequence indication in the transition one.

p b

When reactor power is e.bove the low power alarm point,-the error I

display windows will display only zero, p. <

l

-The RWM low power eetpoint' requires both rated steam' flow and rated feedwater flow to be below 20% of their values.

I

[

id Any rod inserted:.one or more notches beyond its insert limit will

.cause an incert block.to be iceued for all rode withoutlexcepticn.

g l-QUESTION: 043 f(2.00) h l'

Concerning the Rod Sequence Control System (RSCS)' match one of the Switch

'~

Politions or Methode in Column "B" to each Switch in Column "A".

.l

. 3..

SWITCH / CONTROL SWITCH' POSITION / METHOD ll

' Rod Sequence Selector Switch.

1.

NEUTRAL h

ib, Sequence Mode Selector Switch.

2.

CENTER k

[U o;

RSCS Bypass.

3.

WITHDRAW kl de

. Start / Abort.Togele. Switch.

4.

DEPRESS h:

6 5.

B34' s

r

!p i.e' n.

l t

im (a 1;1 t

-.J Page'23 t[, '-

! QUESTION: LO44 (1.00)

LChooa'e the signal that does NOT-ehut Reactor Water Cleanup Valve MO-15, RWCU-Supply-Inboard Isolation.

t

,RWCU'High Flow;at 200 GPM a.:

~

jb.

LActivation of the Standby Liquid Control System.

c.

LEWCU. Area Ambient Temperature at 200 degrees F.

"d;-

Non-Regenerative" Heat Exchanger outlet temperature of 140 degrees F.

(QUESTION: 045 (1.00) tWhich ONE of-the following describee the primary concern if a slow tube leak. develope 1n:a RWCU Non-Regenerative Heat Exchanger?

~

a.

Injection 1of REC corrosion inhibiting chemicale into the RPV

.b.

Colder water;being injected into the feedwater system.

c.

Radioactive. contamination of the REC system.

Ed.

.Oveiproceurization~ of the REC system.

QUESTION:: 046 (l.00)

.A Transverse Incore Probe (TIP) becomes' mechanically bound inside the.RPV.

Subsequently, a-steam leak incide the drywell results in a' reactor scram andicontainment ieolation on high drywell pressure._ Which of the following describen1the TIP eystem design feature for isolating the containment in this aituation?-

a '.

The Shear Valve must be shut manually.

b.

The Shear Valve will automatically close.

.c.

ThefEall Valve will automatically close after a precet time delay.

d.

The' Ball and the Shear Valve will receive automatic isolation aignale, but only the Shear Valve will provide isolation.

p W M p F W W W M # W A W L 4{ Y Y $

M*

% 0 lch h+'%^MWM V

%M<9 Md khY ka$NkhklNRP n$$$$?

%Q W,L'

~ "ilA T'

' N,"

'+P gh n %>Rn

=

&p mJW v mm. v. p-

/

wh;yyqu W 7 &

A

.2

+.

t

,%y *= m?..

24 s>

=

ywy m m+

, 2s an m

~

m,_

u

' - -.+n a.. -

i

,!. nwpg h i hb.

W 3%, M. ' * ?

' y $"

w, t

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m.

e

~c>

mn.. _

mgy pf Q~ x Q Wcl h '

Y$

.xl llb l

a O'

W4 2

l [ 'QI j

Y W

A

?

~-u-

...s,

$w,dlUESTIO M

,"m.

Wlm,Q.

iM

.+

m.

,+

g

. p~.

047?1(1000b %

nyu mm. ; W: - = n. c%w ;Mf v

ym a

y mw s..

w r n.

y~,

w-m MWhichfofithesfo11owing : conditions; requiro 'ai LPRM.Jealibratio. nNe,ing2TIP7f ;,' c ;3 nga 3-g n.

,2, + y

~

me 8

. ~, -

r v.

e

,s

- c __ _

p,:+.+..

z-s

.e<-

m.

O e

i.g., s.

g g g 3 T w> ~?'w 3

5 ofcpowerf operati nsm,a= bovego%ipower sineettherlast

M@%e realib.eeksp.

p w'.

, em'J i

c; o

o 4

s i

rationn t C

il M

fMj ; 'jbyg,

' io \\

n oe

W W N,[4{

.3 s

m ty, 4

l

$m yf g!Ksusstord6'aNupM.fterkbSing-' shutdown? greater 3than 30Nddys>b '

b

.f t <

- Ma,';EA,imsdorhoontrol(ro,dipatternJchsnge three_ weeks after the.lastl' '

' ~ ' ',,,

y W J?~~

~ =

n m

3 h.

. +.

+

w y@$uVl, M dealibration.;

N 4

~>

i_.

_ O

~c vb -j

\\"-

2 i

"yi

..... 'y a z.

,c

.j 5,%dhn, W TwoMLPR'MeSinfa bp,ertical(stbingldiffsrfby: greater thant 5%..

m o

~

aw,

3 s

aw:;gy s

,1 y..

w, w-p u

t-p7, a

s.

c gii a's 94 s

e g%..J?UESTION:l048 F.(1.00)1~

x W

,~ %v w

r; 7

.n

%.c s

+

Q' gf isc.3 vi' f

N, _ _,8

~

g,,

1 g

,4 JN.

,N W Which?of thel.fo...,

MyENTILATIONrsys.l.lowingf act. ions ' occur: AUTOMATICALLY a..fter the 'CONTROLtROO. M ss modeW y

temhreceives.-ateignal?toYahlftGto the'emergencyJbypa.

n gyps

1

..1%

"W c

...A

~,

3 t.

e

,,..,..-oiletcexhaustjfan'

.1 M,sQ AThe5emergencyTsupplyf fan' star ts', fand; the cpantry/$" y g/' %(W

'Lhrips.m

~ '

L

~._ m p.,

7> -

1

.'w,

r eM f An

...L t/

1 9-M D Whe $$lakb va Nes aut;odhtically shift!, Land thesnormalisupplyMansi

~'l[ y 1

1 9d f

5 d

w% p $ i % I 4 p 2 >

~

L x'

L-M47 JThNernergsncMaupp1Nf6n4stiartedarulLtjhe norma 1L, aupplyjfansitriN,

N m,

s kk$(dM. };; hykNThe7 Emerge,ncyJeupplySfan0 starts LandT'the Antake. valves visolateRou_ _tside.q

%d.,A

_ y y_,4

~

?,

7. ; e h/%j iairp

]JC i

~~

gj

~

s q@ @ Q 3 8

y 4-yy 7'

40 4.

1 s

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yvp,g g

_w m

w,g s

h QUESTIOA dO49l jl.00h ?

'r a,.

-;I,.

6 VfkrConc'erningd<: hel ReactorpBuil,dinglVentilation; System (exhaust pl,enumiRadiation

~

T F MonitoringUSystem, Which(item;below represents 7therMINIMUM logiolto auto-Ol1 9sEtar,t2theiStsndby-Gas)TreatmenttSystem'.

N hw V$

M MM~C ~

ww %n;( Two b channele 'INO. P.

p@m % m ' Lone.behannellDOWNSCALE. : TRIP; e

R.

k Ram 4

d m

m kMd$.,iOneichanne11HIGHTRIP.

w y 1,.

M,, g..d ?. sTwo1 channels.in HIGH TRIP.

_rg7

+

.e k,

I

'l n m yy,

VT 1, %

-'{

LamTw.

9 Q['

IJ s'

R~ F n

~f

).Tf) 6-3

,8-

,~

4

.s MU N

l; h

J VM W y N r*

I v:qp'e - 3 3lk W, p a-@.~,

BW1

;3 WY %,'

ld h {kj g " g"g &n Q 3

}

we -

,t

, x.

y

my y p m mm77%9W S-n cWFWug:ny

m. w%w -um A~p &x,W +%%w =;

A u- >:

+ >

u gs.

ys

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$$96% Mind @he: cauo'e is unknown.

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A 4

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Pag: 27 QUESTION: OSS (1.00)

Acouco the reactor at rated power when a fault on 4160 V bue IF cauces the the bus to deenergize.

Choose the item below which describes the effect'on the containment isolation eyotem (CIS) actuation logic.

The containment doolation eyotem will not be affected by this tranaient.

b.

The Division I containment isolation valvee will receive a close signal.

.c The outboard containment loo 3ation valves will will receive a cloee signal.

d The inboard and outboard containment loolation valves will receive a close signal.

e

[ QtJESTION: 056 (1.00) h Which of the following CONTROL ROOM reactor water level inetruments will be K

v111able to monitor / control RPV level during statione blackout conditione?

7 I

Fuel' Zone, Narrow and Wide Range could be used.

P

[

b, Only Yarway type detectore.

7 L

c:

Wide Range indicators (Rosemount type) only.

[

d>

Narrow Range (GEMAC type) indicatore only.

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QUESTION: 067 (l.00) s

}

Which of the following CONTROL ROOM indications /methode should be

$D used to-verify that all control rods are fully inserted during etation y bl1:kout-conditione?

hl >

Green' control: rod full in indication on the full core display for all

. control rode.

y

,b.

APRM downecale reading and negative period indication on all

?

chanr. ele.

,k

$f c4 The REFUEL MODE PERMISSIVE light illuminated when the Reactor. Mode ewitch is in run.

d.

RPS ecram indicatione for both channele A and B.-

.QUESTIONi.058 (2.60)

Tha reactor le operating at full power when grid probleme result in a loss i offelte power and Emergency Diesel Generators fall to start.

An ALERT

'hae-been declared Match the correct TIME REQUIREMENT in column

B" to Joach ACTION in column "A" (NOTE: a responee in the TIME REQUIREMENT olumn may be used more than once.)

" A

"B"

ACTION, TIME REQUIREMENT LNotify the NRC.-

1.

Within'S minutee.

b.

Personnel Aceembly'and 2.

Within-15 minutes.

g-- f.

zAccountability completed.

3.

Within 30 minutes.

m Notify Nebraska Civil i

Defence Headquartere.

4.

Within 45 minutes.,

o<

'd.

Reclassification of this S.

-Within 60 minutes.

event-(aceume N0 ouccessful p

' corrective actione).

6.

Within 4 houre.

Nn IActivation of the TSC completed.

11 y

l.)

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29

. QUESTION: 069 (1.00)

'A reactor etartup was in progrees when immediate ebutdown wao required it::r diocovering that the KHR cystem (Shutdown Cooling modo) was in operation with RPV dome preseure at 100 pnig.

The engineering etaff has finished analysing the event and determined that NO damage occurred.

Which f the following describes the LICENSE requirement for the reactor to

. remain shutdown?

Transient analycia of this type muet also be evaluated by the vendor (General Electric).

b..

Formal permiccion to etartup the reactor must be received from the NBC.

a Wr' tten notification of this event must be submitted to the NRC prior to reactor ctartup.

d, Deviationo from General Plant Desigh Criteria require an independent cafety analyola.

QUESTION: 060 (1.00)

-Actiono to mitigate an Anticipated Transient Without Scram (ATWS)

r::; in progreso.

The turbine in tripped, six Safety Relief Valves (SRVa)

~re manually open.

The following conditione exiet:

Reacto'r. power..................

30%, decreasing alowly Reactor pressure................

900 peig, decreasing elowly Reactor water level.............

-35 inches, eteady Suppression Pool temperature.... 105 F. incroacing l~

Suppreselon Pool level..........

-1 inch Which action below would be moet effective in reducing the heat input to

,th? primary containment?

Increase RPV water level.

[

b.-

Increase RPV pressure, c.

' Increase Suppression Pool water level.

d.

Initiate torua spraye.

l 1

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Pcg 30 1

QUESTION: 061 (1.00)

A reactor ecram was caused by decreasing RPV water level.

EOP-1, Reactor Preneure Veecel (RPV) Control cectione RC/L, RC/P and RC/Q were being

. performed.

Five (b) minutes after the ceram the MSIVe isolated and RPV

'precoure epikes to 1100 peig and do now controlled by the RPV relief valves between 1015 and 075 peig.

Which of the following procedural actione le

. required because of the MSIV closure / RPV pressure transient?

EOP-1 should be re-entered and all etepe should be verified or performed, b.

Execution of EC/L, RC/P, and RC/O ehould be continued with emphaeie on RC/P.

c.

Emergency RPV Depressurization is required, step RC/P-14 should be l

performed.

l

'ds Execution of RC/L and RC/Q should be continued, all RC/P etepe should be verified.

l.

QUESTION: 062 (1.00) f l

Durins power operation a fire occure in the Cable Spreading Room.

There

- r_ reports of thick black emoke obscuring all visibility in the area.

Emergency Procedure 5.4.3.2 Post-Fire Shutdown to Cold Shutdown Outside Control Room,.ie being executed.

Choose the item below which describes the-baDie for the decluion to evacuate the control room according to EP

.S;4.3.2.

The fire has been burning out of control for greater than 15 minutee, b.

The Alternate Shutdown Room and other local control statione are manned.

o,

'The IMMEDIATE ACTIONS of EP b.4.3.2 have been completed.

d.

Component operatione from the Control Room are being affected by the fire.

J-D

y Page al QUESTION: 063 (1.00)

The reactor le operating at power when it becomee URGENT that the control room be. evacuated IMMEDIATELY.

Which of the following IMMEDIATE ACTIONS tehould only be performed if time permite, according to EP S.2.1. Chutdown From Outcide the Control Room 7 a

Scram the reactor.

bL Announce the event over the site paging eyetem.

Obtain the key to the Alternate Shutdown Locher, d-Direct Operatione perconnel to assemble outeide the Control Room corridor.

QUESTION: 064 (1.00)

Plant ehutdown le in progrees with reactor power at 50% when all drywell coolere are lost and CANNOT be restored.

Within several minutes, entry into an Emergency Operating Procedure (EOP) will be required. Which f tho'EOPe will have to be entered within the next several minutee?

EOP 1 (RPV Control) ONLY.

~

b EOP 2 (Primary Containment Control) ONLY.

Both E0P 1 and EOP 2 ONLY.

d>

E0P-1, E0P-2, and EOP-3 (Secondary Containment Control).

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g,The;PRIMARYiCONTAINHENT2 PRESSURE LIMIT.. curve:used in EOP 2, Section;PC/P~

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@% feeti(horizontalEaxis)cthe: pressure 11mitlAn reduced'totallow for;the-Prim'ary Containment Pressure Control,risJehown;below.

Between 9.61and 56.78.

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&,y et2 tic 1pressurerhead-lof{ water;inside primary containment; Which:of;the:

f?ll'owingiexplains.whyJthe pressure limit becomeeJoonstant after Primaryi O? Containment:WateriLevel. exceeds 56;84 feet?"

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- n PRIMARY CONTAINHENT WATER LEVEL l(feet) s N'.

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J.. W d. M. ;3Abov,eiS6;8/ feet, water will be= drained through the drywell vent-a 4: :"3

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AgBOPf2 hSection1PC/PD Primary.~Containmenth,y. Control.1 requires' m

W performancerof?RPVfFLOODING-(EOP-1;; Attachment 1)?if containment; s

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$ pressurelesceedsJthe: PRIMARY 1 CONTAINMENT DESIGN PRESSURE.. Choose thelitenn J

% whichtdescribeefwhynRPV FLOODING 'must; be performed ~ when this 'limittis-fr M excee,ded,.w<. ' ", ~

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M@MENTolpreven t y ch,ugging ; and J eubsequenti con tainment Naliure s g; y xO W

M 4WdP %:ToBterminate4 energy addition to the containmens.

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V IM SomesCNS.EOP16peratingflisit eurves areEgiven in' column MA % Eashicurvet M$15:Ri graphuofitwo. plant $parameteraL(X and;Y axes.of each curve.) <0nepoff A Qathisevaxes11sigiventin/ parentheses,afterthe.limittcurve.AnColumn?"A1 i L4 V Matchlthe:other paramete nfrom columnL"B" which definesMthe specifiofourve ' '%

Qin?columR"A". 3(NOTEigeach-response ln columni"B"Jmay'be'.bsed"moreethani '

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plJ. ' b , 4 1 M ' PA"4 ~ "BF ' 'iM, J. k a 'e 17

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%v g . - ~ W. 4f, g%u::EOP(OPERATINGL LIMIT;-(Curve)? .. PARAMETER j R~ a &+&:cos u'^ l p, ~

n o

. ~,... ni" ~ ,g h< g -u su s Ep l Heat; Capacity > Temperature: -'.. 11,

Drywell temperature f$pU

% Linii tW ( Supre ssion LPo'olt Temp.' ) ; i 'i

n 4'W Md#P Y'

r2 e Drywell?Pressurel $@ @n$ ' M iPressure 8uppression' Press. E e' \\ Mm. +.3,lLimithy (Drywell - Press. ) ; M L3? _ ~RPV Pressure 3 g m. ,n .v wmm g 'x R DrywellMSpray Initiation VTemperaturel %g M~1c? 4.. ~ Torus Air y ALimiW(DryweIb. Press.)t =pa;vma g,m-m ,' o m. MdB ? Suppression Pool Load? Limit-5,

Suppression Poolm 5 l

+' kh %ki d 3 M orei Spray [NPSH Requirements 6.- SuppressioniPooli h%: mmg ' i(Cgre SprayTPump Flow') ' Water Leve1L a + 0 %- -F 4L WW $6 7. Primary: Containment-. p@ b & 9, Water Level m .4 i

aN@&f;i D -

L 4 y c-4 i q bk O, %. meg. $ll0. YO ^ i _ m 4y f T mwyg:. ' M1 ,'4, w .y e s GM, - e v.: p n u v+ .H. QlWyn % > ) u..h x += 4 p@mW: wnm' Mn,;:%r - sv g ,3 M' ..x y y tv kh hfb Y~ b L

W@$NN[hRR f((& NQ? ' L ll_l Mf,K _ k', '?K J B ?l [Nt-4 ' ~. ' i 1 ob ,n o r y ; ,.g %.,p,' +3 JPage:35' y ,w + s

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l. ; t .. =... }' 1 ~ M The;reactorow'aa3operatiingiat power whenia-Station Blackout occurredh JBoth= LHPCIrahdiRCICohave--failed totoperate. RPV wat'er.levelJhas been_steadilye ~

jidecreasing(

WhichTof i the following L RPV conditions: indicates ' that: STEAM ~ ' s ? C00LINGMin thefONLY meanelof. adequate coreicooling?' t .c w s. M b RhV waterjlovel below"ActivefFuelE(belowc.indlcation)',.RPV pressure.-600j>+ Wi f '"T jpsig,3. M a [@gy4 { 4 T800[peig{,' ~ 100 in.,TAF),iRPV;pressuref y bb < hRPV waterfleve1[atlone:th'rd' core [heightl(1 i i le 9p#.. m .. p.m a,.. w M9 'JRPVEwaterlleveliat-Top'of. Active Fuel (0 in. TAF); RPV pressurel 950 0 J H, g yl.-l;psig~n, m n a W. a{gw. '. J ' M.Pdk '. RPV; water 1 eve'1 l at -37. in... RPV precoure.1100 psig.. J 4; <m f,itt,,, m i;f -c = + y -, ,,. hA. ;7 ' m.

QUESTION:a070D ;(.1.00).

,fam %s ; / o M WhicN'of5the following.postvaccident' conditions requires' s $ 2 xecution ofJRPV FLOODING 7.. ~ ~' n W e > j, pwe. ^ J%if&. ' Dr ll pressure:reache's; Torus saturation; temperature.- .m~ y,[' ' 1 ( 6 p un M b W ;NRPVLwaterilevel,cann.ot be maintained:above TAF. ~ yr s &mp s[ JRPVI.sater? level cannot be determined onlany'instrumenta fo, o wm c. g; p,. I r g E q% 4 1Drywellipressurerandlftemperature; conditions reach s'aturation. h~

ll M

.y kz p ' n4-t y$5 y &) b i-' M;. _ q + i ~ L ti Q s 1 >...t 0.. G, - ',& c _l < ;{ - l 2 4. .,-p '3.flc?u ; g t_ b ? l bj.. c ^y .p :. a 7 p dg( > (;r-- vs < , '[..f -. -, ' ' 'c '.$w- - 7 '[ f j si y an g 3 yv +

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.4 '- Pcg. 36 QUESTION: 071 (1.00)

ATWS conditions have required entry into EOP-1, RPV Control and performance f LEVEL / POWER CONTROL (EOP-1, Attachment 2).

RPV water level is being maintained et 15 to 20 inches above TAF when it is deten. mined that EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. Which of the following describec why RPV injection lo stopped before deprescurizing the RPV7 Exceeelve injection may cause preocurized thermal chock resulting in preocure veecol damage, I bc Excessive injection may cause a large power excuraion resulting in core damage. Excessive injection will result in cooldown rates greater that 100 dege F./ hour. d2 Excessive injection and deproecurization may cauce excessive RPV water level ewell resulting in Main Steam and Turbine damage. QUESTION: 072 (1.00) During refueling preparations, tools uned to. remove veseel internale r1 being removed from the pool for decontamination. The refueling floor f Continuoue-Air Monitor (CAM) has just alarmed and indicates at the alarm tpoint. Upon hearing the alarm, the team ~10were the tool that'has just s b~_n withdrawn back into the pool Which of the following deecribee the i f Immediate Operator Actions that are required by EP 5.3.5, Refueling Floor H1'h Radiation 7 Entry into EOP-3, Secondary Containment Control, is required. l Jbc ^ Verify eccondary containment radiation levels are lees than 10 mR/ hour. c. Actione chould be taken to verify that contamination levele have returned to normal. ' d ;, The Refueling Floor la evacuated immediately upon hearing the alarm. L L l l l L l 1 l l l N ~ l mhh %h w ' W._ _ - I

fr$gy.eyk ff?W %?{k? (*' "p + - Y' 1 m ~w < w

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~ g 'e Df. g,.,mn m q;7 g:h y s , Pag) 37c gep gx:v. r 1 a. m. e y 7,q [Y ~ " ~ Y' e s. cp, s . 4 r y 1 ;. -. a.. _. " QUESTION 6:-:0731 (l'.00)J g ln.a - + '9+Ln~

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...,_.s ~ s .. iDuring post; accident recoveryLfrom a largeiLOCA,3the decisionDis made'to B 'ventethe?drywellsthrough the reactor?buildingcvent,to reduce hydrogen / j M oxygen? concentrations.1(Which of the following release rates.throughtthe. feTreactos building Nent9 require entry-into E0Pa4,' Radioactive ~ Releaser

h Contro1?V
yr

= m gg Jf , 9 :y. .8 e + 1 f g f 16 E13 uC1/second;, - s p$h 5 n 6 5LEf41uci/.second. i $. li NM e 4.1Ef5TuC1/second. : _ a x n- - - e

9. 8, n. p,..

1 4 .,.o ?Mdp.,63: E' 6 uci/second. w < &j '.' ~ [ ~ '~ A: fc < % i, $D bESTION6 074 d1100)b.

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1 [-,,* y. t -C ' - 9H Th9 react 6rLis,, operating _AtfpowerLwhen a[ Service Watersreturn. header,;fromi*m flRe?ctor1EqtilpmentiCooling 1(REC) Heat Exchanger '1A crackst and ~ starts fillingL , ~ % lthfadjacent QuadranteSump. The leak'cannot;be-isolated without' securing ~ o @ / Cooling?to therREC system.f The,other train of1 Service Water (l'sJout'of: > T rviced LPlant temperatures are. holding steady._. The: Quadrant 1 Sump header " p ..c~ $ Jidolati'orivalvef is~ stuckJopen.1 iWhich of the following-~ describes the actionu 4 s irequired by E0P-3,: Secondary Containment Water Level? Control,Lifithe sump., Mp;sHaximum:Normalt0peratingLeveltieexceeded"andicahnot-bel restored 73, '

M

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o ueioperatingesump pumps.ftoL i'yfand redubeithe sump-water >1evel;

Contin.

t Q:.JV. -.WW.. ~ I 4b(,

Isolate:Gervice:Watersand conductlan~-EmergencyfShutdown Fr6m:Powersper..

g11 ' - 3GOP-2.1;5.g y;, m. s , + 9 a. &g p JcE,

Isolate (Service Water,' enter E0P"1,5RPV Control, and execute'it7 i

' concurrent 1y'withiEOP-3. 1.. -s 4 y,m n,, s./.. 1.'..... @1 <. id.o,;EmergencyfRPV+depresourization is: required, enter'EOP21 and; proceed 7 4 u, , tairectlyf. to step lRC./P-14. - a m [A 1 (fk'g % > c 5, ~

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e, ,c, y W9.31W ...If. O,, Q-: ~ ~ s QQUESTIONR07p;((1.00)! af t 4 m ,a u x , t W.#Which of thelfollowingira....dioactive! waste: collection tanks lare xe a ,m @-Q normallyflined up'tolrecelveyflow from1theiRehotorJBuilding.. N Quadrant? Sumps?',4 m y w a" m- +. 8lX ,. { 9,;.... .m 3 jd ! + 1 3!

h;;;, % g FloorlDrain Collection" Tank'.

~ ( + r Wr s x 5,s. '!aWasteiCo11ector" Tank; 1, 1 s- % :y@ 'FlooN, Drain Sample Tank. m,. 4. w s'. V g :# 6 &q s a _s 6- "A-rs p r p%di;:-i lSuniptDrain Co11eotor;Tankb e i 'g f n ,. =, a,;. . w e n .w> p, g r ',, rc. y 7 q y 1 d QdkSTION M076Ll(i 00) - x' M- ~ ? %z ^ v 1 f 7), y, l ~ ' N ATibingVsystemfrupture,isicaus'ing water;to drain into oneToflhheJ s @Rea'otor vBuildingi Quadrantf Sumps in; excess t of:: the : sump pump # s' capacits. - Thi ' t @MWhich(ofi thetfollowingldescribes where continued drainage flowh sumpei~stfillin'Eup,<andthas dustLpassed the HIGH 'HIGH alarm setpoint.b g F ~ wil1V.,;accum,ulate? 4, s g. y O g' t ; s 3 '-Thefsump wil1[o'verf1'w#and"startTf1111ng;the room.above thel; sump. M, e yw ~ ;n,, - c:a o 1 i ~ . E Ob,':;

Dr,..ainage: will'be directed (to'an adjacentJQu.adrant Sump;

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, u, M MD,rainagelwill-be direstedito'the Drains Oveiflow Tankl m% W y mv e g; - DrainagoN1117betdirected to tho' torus. area. lL /3 ' - a -h } If i 'm .s v MdE$ TION: 107711(M00) 3,p 3y? ' hlIbohof(Ihetrument?A'ir,1EP-5;2.8,:1 requires:thatLfue17 handling evo'lutionsLih, 8 Ipro:ress-on-itheirefueling flooribe; stopped; . Which of.the'followingi f %ldieribesiwhyfthis" action 11~srequired?-- ,m. Ik l- , [.. f y.J.>? LRPV?'integrityL(MSIVs and SRVs) may bechall'enged., J x-.... $ hy g lThe(SecondaryoConta'inment Isolation" System may beginoperable. i p

yg.

Emog 1The~StandbyfGas Treatment.. System: requires-InatrumentLAir forfpropeM @M ~ coperation. ~ ' 3 p-s ,y; y Mdb cRefueling? system' interlocks will not function properly without ph5 ' adequateilnetrunient Air pressure. d; y; D_f f"7"L ks, s. di ^ w QR NW Nfbkuk ~ d e nn w s' ' . y .$1 3 %f^2 ' & y 3 9, 5 h;(.1

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- w g51 m s 6 4 ?! ya e, - s if;e.-...; ~ ..-( 4 t. s ,LQUESTION:'078 -( r. 00 ) ' "d + J w;m,w.., e yn, 'n 2 ,m QR Whilelthe reactorfia'intcoldLehutdown:with;RHR Shutdown Cooling (SDC) Fin;, pM M operation;Sant error;during adeurveillance;teet: caused the:Loperating{RHR d@Opumpia! Minimum f F3 ow' Valve" to: open.decriasing reactor water. level? Which ofLthe folloq Auto'atie: isolation occurs from i m

3. @

s M is %e3uiredlby:AP 2(4'.2;4;1,4.Losef ofe %utdownL Cooling? r " L w: '.,, i tior a r. y s se e ,~ n s. y i 4 s .,_ H o n eactor?:wateretemperature.- RQ um, 8, f,.t:- n..,;,. y y 7 7 +

Q by " Verify (the - pump.1operatingLin4SDC. tripped.-

w g cw ,q p 7 g4 =. r @@g,.. j d &@MShiftvRHRsto:the injectionimode.7:. :. d + m j . m,.%. 8 CLOSE2RHRrMOf13AW BE C, and:Di.if OPEN. T m c S ww s m $g$:..... [ H(dUESTIONi/0700 2 J <a, z ~ y ,y w (1.00)f u .y S M/M 1 ?_,.'. M Wiille. fin;coldiehutdown. RHR Shutdown 1 Cooling is' lost"Bue to acheati, L Y. Y g xchanger malfunotion"and'cannot be'immediately restored.: Which of-the :. J'"'t ~ A f611_owing11snidentified asLSUBSEQUENT.0PERATOR ACT10Nein AP:2.4.2;4.1;tof '"q a S d istiin heat' removal?from1theSRPV7 ' J M.~ 6 %6 '.Feeidihs%nd bleeding;the[RPV. 2 _Fd w m m 1-w o M_ $,. e r Makimizing1RWCUJflow'andDc.oo11ng.. ',P k i f t c' bi %y%c4 drywell.' cooling;. i Increasingi le w, , $}, - =, , f >J 5 4 Ed

9.iRun W. ROM.CRDipumps.z

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$(k' $ffff?N$ ^? ' h[ ?' $ ' ' ' y f= p ? 4 's-i W s. ; gG+ w u m, Av tv, .,e. n n. :wQ;(% o + e n + + f. < y N @z "A p' !3 $.= ph "-.' N.. $P'- + - pagy 40-u .ym [$g7p%x x : y%% s n 'e 4 .c ~if f ). 3s ) s" Mc, t-, M ~

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s v,:g ::x. w. > w;. i. o c c Swp n ' n n x ny cme.. ~.. a.,..s sn .v 2 ww WGUESTIONdO80:;J(1;00) ~ 4 w w - ~ g{ .,Y ' ' z p MTh'=eareactor wasYoperating?at power whenLan improper 1 & C surveillancej y (operatorferror)? caused both Reactor?RecirculationL(RR)LPumps,to' trip. <The, ; y$followingfplant11gformati'onfis;observedafterlthe.RRPumpstripped:- - w +:h 9 Power:0"- 16% ; stable' cu w. 4% ' (JRPVJLevelN15 finches,iPre'esuref :920)psigiastable: hi > y;..1 % / W Contr.ol;RodrPositidn:~pelowly;increasings b LUnchanged. ,X :: 1+ s% y- ~ a. %, 4";' 'Alf: othir'paramet'ebs/ equipment:, l Normal / operable i p J-y n ww ~ r 1 .,fi..--.q, a,,*,- A M:lWhithfof thelfoll lowing cou,rses of Laotion61s: required?J 1 I;;e.(j$ ' NEntersbOPf2.102bH6t!StartupProcedure,after.thecausefof1the.RRL, ,c. k [l,e,p 1 (tripj has;been deterinined.n . 1 A, t .t. t ? h@!GT.r.(bi 4 Ain'ormalb reactor ~ahutdown'should'be' performed using.GOP M Shutdows FronLPoWer.; a v m

g..tr 0

,p; @ ', eUOPl 2 1,;5i: Emerge.ncy Shutdown. From. Power, - ~should"be entered.' ' j, + .,, ~ hgug d g "g, a.... ~MEOP-Ik RPV? Control,!should betentered. + ~ ymm (!dlltg %, m B K,- 2:q 9 I.%,, / , ~. [- 4 7 f j i Q.* I E n( g i, u i 4 4' t i ,g bW a. Q f: 'i_.. sy u. r S 4 l&p, , ~S._-g

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~_ -p, Page 41 l l QUESTION: 081 (1.00) Plant startup is in progreso with the reactor operating at 20% power when an electrical fault cauces Reector Recirculation (RR) Pump #1 to trip. The

Reactor Operator reporte that indicated Core Flow is less than the Natural Recirculation Flow Line.

The following plant information is observed after -the RR Pump trip: Power: 15%, stable RPV Precoure: 93b peig, stable RPV Level: 35 incheo, stable Core Flow: 26%, stable All other parametere/ equipment: Normal / operable. Which of the following courses of action is required by AP 2.4.2.2.1, Trip of Reactor Recirculation Pumpe7 a. Enter a subetitute value into the PMIS computer for core flow, b. Increase core flow above the Minimum Recirculation Flow Line. c. Trip RR Pump 82 and conduct a Normal Shutdown From Power. d. Scram the reactor and conduct an Emergency Shutdown From Power. QUESTION: 082 (1.00) The reactor is operating at power. ONE of the two 250 Volt DC systems hao juot-lost power. Which.of the following concerne are caused by thie lose of power? a. Control Room annunciatore may have lost power. b. 4160 Volt AC breakere may have loet closing / tripping capability. c. Process radiation monitore may be inoperable. d. HPCI or RCIC may be inoperable. 9 -._.-.-__m_ _._____._______.m._m.__

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f~ w y:; h %,, ,A M pt-QUESTION.E 004jl(1100) 4 m -l V ..\\. 3. ' ?.,, . \\ p):$.:FJfrfMain?Condeneeridecreasing1 vacuum, which~of thetfollowing? condition's: .a C roquire an9IMMEDIATE: Main,1 Turbine trip?

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n f i Pag: 43 QUESTION: 085- (1.00) Poet accident recovery la in progrees from a eteam line rupture inside ontainment. Primary Containment leakage h s led.to high drywell temperatures and low containment pressure. The following plant indications exist:. [ Power: 0%, all control roda_ inserted l , RIM 7 Level: 50 inchee, clowly decreasing -RPV Preenure: 60 peig, etable h: Containment Precoure; 3 peig, stable l; Drywell Temperature: 300 F, elowly increasing Torus Air Temperature: 130 F, etable Which of;the following actions is required oy the EOPe based on the plant indicatione provided? ' Initiate drywell oprayo. b. Flood the RPV. c, Vent and purge the containment. { a ll d< . Initiate Standby Ligwid Control (SLC). b k!' g QUESTION: 086 (1.00) P: :ti accident. recovery lo in progrees from a -loss of drywell cooling. The Drywell Spray System in NOT operable. A small ateam Icak inside L containment has.also contributed to high drywell temperatures. The [ 'following plant-indicatione exiet: ~ Power: 0%, all control rode incerted -RPV Lovel: 50 inchee, slowly decreasing RPV Pressure: 650 pels, stable. Containment Preceure: 15 peig, slowly increasing Drywell Temperature: 300 b, slowly increasing Which of the following.actione is required by the EOPs baeed on the plant p. ,indicatione provided7 y p-Initiate Steam Cooling. b. Vent the containment. c. . Flood the RPV. f ~ ' di Emergency depreeeurice the RPV. r v _w bAum

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y 7 Y b y y$GUEdTION0875i('1)00); - w y j m g<r j., %Eich[seetionbof"EOP3,Sec$ndaryContainmentJControl,<requiresn 1 W thttNoertainfactions beitaken when key;parametere(exceed.11mitsjin'. hidesignatedsecoddary;containmentareas;;1Whichofthefollowing; conditions' MrequiretEmergencyRPV_Depressurization?'4 sc - m a,, --, 1 w r .~ h@g 70NE' 'arealt'emperaturel exceeds,its. Maximum. SAFE Operating Valuel W A wen, ,- 1, ns 4 4 'n ':o-p

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v- _-O,s M,bs .LONEiareastemperature exceeds 6its Maximum 1 SAFE;OperatingJ Valueiand::az y M G(iprimaryisystemJioEleaking(intoithe area.i, W A:Mw ). ((j$[hMdreithhnob,e? area"temperatureexceEdsits1MaximumSAFE! Operating: n, ' ~ q w gy,M-<,iValue. 2 %~ Mia 4 ,W .1 - < s m N TdW More'than;one area._ temperature exceeds its Maximum: SAFE Operating 4,, s ' M@V > j. s Value/ and af primary, system io. leaking 'into' the area. n ~s p e jC +& .7-lm m o 3 '5 N 7 i, [.' =.. 4. . 30881-(l'.00):. '^ OTQUESTION: .. /.. ;,. g' d V '.1 L + n 3' 1 _.. 3 i ~ 4 K achlsection_ofLEOP-3;(Secondary.Conta'inment Control,. requires 3 9 thitteertainiactionni.be1taken1when key temperatures' exceed limitstin., de$ignatedfeecondary'Econtainment areas..Which of;the-following is'thei @($:l MINIMUH f o'on, di tioiiireduiringi entry s < intolEOP-1,.RPV Contro17,, pp + W,'IONE a'rea g Ad.. 3 - c4 ex'ceeds ite NORMAL OperatingiValue andLajprimary:eysiem is i M ~ i + h e ; Mleakingsinto.? thenarear L m :r T 1,, D MtQ J 'ONEi area? exceeds,its!Maxiinum. SAFE (Operating Value and ~a primabyisystem - gMi iatleaking!;into:thetarea; ,. s M? f f ;fMore5tlan one7 area exceedsiits?MaximumiNORMALIOperatingnValue?and(ah hW A= b $ s lpbimary[e.ystemLis leakingiinto theLarea.- T I %, m,;s m c w w .. +. b _, *d@ ,lMoreithankoneiarenitemperature exceeds.its Maximum SAFE Operating [p\\ENef.g.., [Vsluek.- 4& d IQ;W < ;;f ,,.'Y hs y 2 -hl%ga 'i

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. z.m i VM 2 :D;epress?ALLtVALVESICLOSED onLtheiturbine" control.,'panelk m. Ag % v=c, >w m u ....v i &;gs ,50F W Shut 1the MSIVeLatipaneli9 31 3 % 7-y, 75 cram":;thej reactor -

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l l 1 ilRC LICENSE EXN4II ATION HAriD0lfT EQUATIONS CO.*lSTANTS. NiD COHVERSIONS 6 '= m*C *deltaT 6=U*A*deltaT p P=Po*10sur*(t) p,po.,t/T SUR = 26/T l T=1*/P+(P-p)/Xp T=1/(p-p) T=(p-p)/Xp p = (K rr-1)/Kerr = deltaKerr/Kert p = 1*/Rerr + ferr/(1+XT) e A = in2/tg = 0.593/tg K = 0.1 seconds-I 1 I = lo*e'"* 4 CR = S/(1-K rt) e l 2 R/hr = 6*CE/d feet 1 Water Parameters 1 1 gallon = 8.345 lbm = 3.87 liters 1 ft3 = 7.48 gallons Density 9 STP = 62.4 lb /ft3 = 1 gm/cm3 m Heat of vaporization = 970 Btu /lbm Heat of. fusion = 144 Btu /lbm 1 atmosphere = 14.7 psia = 29.9 inches Hg. Miscellaneous Conversions I curie = 3.7 x 101U disintegrations per second 1 kilogram = 2.21 lbm 1 horsepower = 2 54 x 103 Btu /hr 1 mv = 3.41 x 105 Btu /hr 1 inch = 2.54 centimeters degrees F = 9/5 degrees C + 32 -degrees C = 5/9 (degrees F - 32) 1 Stu = 778 ft-lbf

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REFERENCE:

L l p 204001A109 ..(KA'n) l l ' ANSWER: 012 (1.00) l: 7;- .. b L r:.

REFERENCE:

h? f CNG Procedure 1.1, Pp. 1, 2, 6 294001K105 294001K105 ..(KA's) Mbewss%a 22 u

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REFERENCE:

CNS Proceduro 2.0.1, Pp. 1, 2 9 294001A111 .. ( KA

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'JANSWER:'

014.~(1 00).

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REFERENCE:

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REFERENCE:

CNS. Procedure 2.0.6, Pp.

1, 2, j 294001A111-294001A112 ..(KA's) J'

ANSWER

016 '(1.00)= ~ 3

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