Text

Exam Rept 50-289/85-19 on 851031.Exam Results:Candidate Passed Section 1 of Retake Exam & Was Issued License
	ML20138B660
Person / Time
Site:	Crane
Issue date:	12/03/1985
From:	Dudley N, Keller R, Kister H; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	;
Shared Package
ML20138B656	List: ML20138B652; ML20138B660;
References
	50-289-85-19, NUDOCS 8512120352
	Download: ML20138B660 (12)
	v • d • e

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O.S. NUCLEAR REGULATORY COMMISSION REGION I

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OPERATOR LICENSING EXAMINATION REPORT

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EXAMINATION REPORT NO. 50-289/85-19

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FACILITY DOCKET NO. 50-289

FACILITY LICENSE NO. DPR-50

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LICENSEE:

GPU Nuclear Corporation

P.O. Box 480

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Middletown, Pennsylvania 17057

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FACILITY: THREE MILE ISLAND NUCLEAR STATION, UNIT 1

EXAMINATION DATES: October 31, 1985

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CHIEF EXAMINER: b.j 7/S

( ,,

//[22/FT

]

gf N.'Dudley, Lea

actor Engineer

date

,

Reviewed By:

.

//b'>Yf[

i

R. M. Keller, Chief, Projects, Section 1C

date

Approved By:

.[

ff

v

M

S. Kister, Ctfisf, Projects Branch No.1

' date

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SUMMARY:.

}

One reactor operator. candidate was administered Section 1 of a retake written

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examination. The candidate passed the section and was issued a. license,

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8512120352~051204

PDR

ADOCK 05000289

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PDR

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REPORT DETAILS

TYPE OF EXAMS:

Replacement

X

EXAM RESULTS:

I

RO

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Pass / Fail l

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l Written Exam

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1/0

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Oral Exam

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0/0

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Simulator Exam

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0/0

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I Overall

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1/0

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DETAILS 3

A reactor operator candidate was administered Section 1 of a written

examination as a retake of an examination administered on April 18, 1985, on

which the candidate passed the oral and simulator portion of the examination

but received less than 70?; in Section 1.

The examination and examination review were held at the Region I office. No

changes were made to the examination due to ccmments made during the review.

See Attachment 2 for utility comments.

Attachments:

1.

Written Examination and Answer Key (RO)

2.

Facility Comments on Written Examinations

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NASTY

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4

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1.

FRINCIPLEE OF NUCLEAR F0WER FLANT CPERATION,

FAGE

________________________________________________

THERn00rNAn:C5. HEA1 TRANSFEF AND FLulD FLO'-

____________________________________________

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1

GUESTION

1.01

i .50:

Which fluid syster is subcooled by 3rer.ter than 3C F?

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FREES.

r.:s,

2

a.

540

1000

,,

e c.

,e,,

.

_

.-~.

'

c.

665

2000

e ,. .v

- . 6, .3

4 ,

t

v. .

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PUEETICN

1.02

(1.50)

Critiesi H.st F;u

'um>

ts cetinc3 s; the heat fla

a',whica

,eparture

,r oc N x i ea tc- .

3.in3 (DND

o c c .ir s .

Ft e r.

.t, n, F . . . t.

i r.

-

s

.

t. c : .

. %

each cf the p a r s.:.e t e r s b-low. tell has the CHF will c h a r.3 c . ( C o n t i .: c t

e s e t. paraneter seFct2tei/.

,

j

Licit your ans-e- t: Ti.CF E A SE ,

DECREACEr

cr

'EhAINS UNCr.ANGEC.

a.

Eetetc: L:: .a r.t i l ;,* F.a t e .

c.

Reactor Cec'snt T e n. : e r a t u r e .

.

!

.

Rescter Ccc; ant Fressure.

C3 G 0.5 es]

1.5-

!

G U E _ _. I u_ r.

1 . v_ o.

2.uu,

hatt act :ns sa vi; c_

t :

r.

t: :. 2 i n t s t n the retctcr : r t t . : s '.

.

follow;ng a s a g r. ; f ; : E n t iced rejectier. betweer. 230 te 280 EFFD~

Erplain uns tats act:cn 13 effc:tt...

.

!

GUEc....2sN

..v-

fl...

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c.

l

A s s o n.e twc equal eaconts cf ne 3s t in r ese t t.. ity are acced tc a reactcr

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I n s e r t i n g i. 3rcup of

odt sn; a s s u n.e tne r e r : t c.t

21 a ri; 1, ; t ; I y cr

2 stable Ecstr.1ve s'titup rat..

If the fir s t red ins rt. n recuccs

,

the startup rate by a he:f will the second rod i r.s e t t s o n reduce i t.e

i

startup rate to :erc~

Euplain.

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(****x CATEG0FY 01 CONTINUED ON NEXT PACE *****>

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FRINCIPLE5 0F N U C L E M. F0WER FLANT OPERAT!DN.

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~~~~IEEEE6675555CEI~IiE55~5EEU5EEE~ 56~EEU56~EEUU

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GUESTION

. 0 !,

(2.00:

.

If initial count rate is N0 cpi wita a, shutdown na a r 31 n ci

5.,

unat t3

the new value for the countrate if t h U t d o w ri n.a r 31 r. 15 t ric t c s s e d tc 41' ~

Shcw n4cthod Of c a l c u '. a t i c n .

,

1

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GUESTION

1.06

t2.00i

-

'

Why coes

enon pe3*. later f c i l c W i n g a 's T,'a t d c w n from a h13h ? <, w e r Ic.el

than it does f c1 1 ovir.3 a shitdrun f i c :t a low power lescli

,t

..

u u t.c i t u d

. . c, <

t

. i. ,, ,

.

s.

Wny niu s t the RCE de n.t i r!t t i r.k; s v o c oo l e d fo;10 win 3 a

reacter trtp

b.

Wh, cces tre GT3C s t e a u.

temperature decresse betwe.:n

-

7C'; ano I S " " t cu- r "

G, , a- . . ., t.

i.co

i - , ,a.

Jr

ilu .

. . . .

._

_

. .

Wnat .sFFear to t c. t it a c c . s t m tem;c store c o e f f i c. l e n t a: .: c r c e cc.cen-

trttien it 2 n:r e be0

E . ; t. ; s i n WH7.

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-

GUEITICH

1.C?

(3.00)

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HOW -cold the actual cr;'.ica, ecc paaltico varf f r c n.

t.a e e s t l i:. -a t y.

Oiltical r c ' po s . t i cr. .EC

f c *- EACH of the ic11cwin3 s i tu s t i or,s .

Incloc( a SK!EF

r. .: ;. l a r- s t, ; . r.

WHr.

!

a.

After a trap i r c rt 100: pcwer" a r, ECF is esiculated using re:c

e r.c n r u c t t -it.

fcr 1

t ,i : Lt; 5 hcur s efter tac + rp o .

. /

b.

The actuel bor on c one r r.t r ett o: 25 100 ppe. Iower t hin t he value

uSec for tae ECE.

c.

20 EFFD is used in the'ECF instead of the actual 200 EFFt.

d.

The source count rete ht; decreased f r o n. 20 eps te 10 eps

between the t i n. e tne ECF was calculated and the b eJ i r.n t n .:

of tne star tup.

.

(4****

CATEGO&f 01 C GN T !N U C C ON WIX T .F A'C E s o n s )

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T H E F.M O D Y N A h!; E. . HEAT ~RAN5FER AND FLLID FLOW

LU S..Gb,

. 10

t o . v u, ,

t 41

. ,

,

State which rod has the greatest INTEGRA~EO rod worth and

EXPLAIN wny.

Treat each c o n.F 3 : 150n SeFBTEtely-

a.

A rod at the center cf the core comparea to a similst roc

s'

the e 3e c# t,e co c .

b.

A roc :reppec by i tself c c e.p a r e d to toe s s ,t. - roc ce:n;

dtcppad dur ing a re actor trip.

c.

An Anial F0wer inaping Roc compared to c centrol ran,

t. U E C *i D r '

1..*.*.

,.t..*,*

o

T

'

.

The reacter is suberttical st

1~

E-3 CP5 when sn atmcsp7eric

cv.,p

fz.'.s

o p e r, .

. ~ 5 c A s t c r.

.sive is openi

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E X. . , n. . s una,

.appent to resetcr pcuer sno . .s

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a.

r-

e

(A;Eu-e

l'.e

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m :.: e r r.c 0 s i s t e ; > a;

E. L r r. .

r. :

e c :; c.

trip cccorsJ

'. Assure tae s s .T. c tr2.;;=at accurs st ECL.

EU L Al . sr

; * f .. r e r. c e s

c

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ir, tre pouar.Ta.e r e s t.

r, u sa a result of tne : r.c r e c s e c

t. .i r r. u :- .

, , , -- - +$ e. u, *a

s

s -

w e

9 -

-

4

- --

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1sw

Curir3 pc ,4:

cp

s t i c r. s

t 2 5 '. - i t ,- three

3) reacter c o c i a r *. patp.

(RCF < I r.

cpeist;an tne 1 ;.vi i r.

F. ; F ,1ccp A; is stsiter.

E r 1 *: f ; ) ::scuss *he tc. lowing

crsmsters cuting the tra. sten.

c

4. ,, r . . . . , . , c. . . . .

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w

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e. .. . e..

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....

Include tne centrol act:crs -- the IC5 wae e apcI: cable.

(***** END GF CATEGOP1 01

- - - m)

isr****

- - - - END OF EXAMINATION ***************i

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1.

PRINCIPLEE OF fiU LEAR POWEE PLANT OPERATION,

F ACE

5

THERnODYNAhICE, HEAT TRANSFER AND FLUID FLOW

,

ANEWERE -- inI-1

-85/10/10-DUDLEi

ANSWER

1.01

.50)

b.

,

,-

REFERENCE

+

j

Thermccynsmics. Ficta ric~, sne heat

T. sn s t'e r (cr nuc.ecr Fawc- ? ; s r. t i

,

ANSWER

I.02

1.50

,

!

,ncresse.

4

a.

A

!

b.

Decresss.

.

.J.e

'C I .

1 . ~- .

,DCrE530.

[ c.

-

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C.

A

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REFERENCE

.,erati s c l e r. c e ,.

en.

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in

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pp ,-

e,.c.

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a;

4

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s r,, e. w c r.

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a

Reactcr Ecuer cust be tocrease: CO.52 to burncut :e n c r. . CO.51

nr-. : : F. = v

r.

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r a t-

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r. c e r with res:,

ity. CO.i]

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AN5WEP

1.05

(;.c3;

$0h*

CO.6]

K1

le 1

=

+

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C v.

c,

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0.04

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CR1 / CR2 = 1 - K2 / 1 - M1-

[0.63

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C p. ..

. e,1 u _ hr .

,f

, _ L, , .,.

.

-

S3 eps

C 0 .' 4 3

100

1 - 0.771 / 1 - 0.962)

=

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k

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k

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.

1.

,PRINCIliES OF NUCLEAR F0WER PLANT OPERATION.

FACE

'

- .

>

THERn0DrNAniCS, HEAT TRANSFER AND FLUIC FLOW

,-------------------------------------

-ANSWERS

L THI-1

-55/10/10-CUDLEY

,

8:EFERENCE

NET 3-11.jp

11 1-2

A t4 5 W E R

1.06

(2.00)

Equillcrivs' qcine is pecpor:1cnal tc Fower, wotic equillcrtum

xenon is,not.' C .0

inerefer you have a h:gher rstic of

1: Xe

at h sher pcwer levels.

The greater the I to Xe ratio the longer

it takes for,suffi: lent 1 te $tesy t o ), e such that equ;11driun.

Production abc ce:a

cf xe is cccurr:ng

(i.e.

the peak). C1.03

p r r . o. . r t m e

r

-

u-

Th! React.cr The e r ,- Lessca Plar, p 49, 54, 59

.

ANEWE F:

1.07

(2.00)

s

'ft

t

a.

The 2.5 F subc; clin: limit insures that the corv. is fully co." ec

,

>

ens snoing : s pr es ente c.

saccounts f or : n str un.c n; e : c : ; t 1. 0 ~.

. t:f. CT S G temp e r a t.ut e de c r e. a s es cecause the amount cf supenheat

'

.

'oecreases due :ecuted heti t:snsfer ares ano te gr eater s tear

steaux flow. C1.0;

i

DEFERENCE

0F 1101-1 p i4i

RCI. Lesson ~1

n p 32-3e

i

,

ANSWER

1.06

.5;/

,

' cc ne : : s ; ,., ; / -: .

. .

- , e rt , , meccers lesa nt3ar.l.c anc car. e v e r< t u a ,i t

s

e

tn

..

AE the LO'NrStcP he t5

U"

ti e W *- s T.s 1 0 n rEnOvC5

t. G: Cn 1o*r tn1

CO'G.

/'

This intrccuces pcsitivc reactivity because neutron a b s c r p t i c r. has

,

been r edu:es.

The enansicn of the moder stcr c l or.e int' o;x e s negcts.a

react <ity.because there 12 less neutron thermali:stico i r, the core.

4

As bor on concerttr ation increeses, its positive reactivitv effect increates

until it nay bdecme greater than the negative contribution due to

'

reduced th e r .1. a ' i e t ; o r. .

(3.5^

REFERENCE

Nuclear Fundanentals

,

1,

.

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\\

. , , . - . . . . . _ - . , , , , _ _ , _ _ _ , -

-

, - , - -

c,

,-- - - . . _ _ .

,

_ _ . .

.

.8

.

1.

FRINCIFLES CF NUCLEAR FGWEE FLANT GFERATIGd,

FAGE

~

-

THERn00'rNAnICS, HEAT TRANSFER AND FLUID Fw0W

ANSWERS -- inI-1

-65/10/10-DUDLEY

ANSWER

1.09

(3.00)

a.

Actual critical position will be hi3 er EC.35: due to Xenon peak

h

after the trip. E0.43

b.

Act:n1 critical positic. wil' be lower C0.351 with less bc cn in

the f:05 the C o n :.t o l Rods *111 need to be inserted to compensate for

the lower reactivity of the boren.CO.43

c.

Actus1 critaral pos; tion will be hi 3ner [0.353 due to le ss e >. : e s. 2-

reset:vitf remaining in the core at 200 EFFD.CO.43

d.

Actus1 critics 1 posit:en will be tne same [0.353 since in:tial

c o u r. t rate ., a -

.c

-: f f e .. t c c. t. . F icnt, pcuer at a h i c . . E e, r.

cor si .,

.s.-.

-

,

REFERENCE

ruclear F ur. c s .~.c r t a l 5

n N s. . E .

. . . .

. a. . ...

.

,.

.

-

..

a. Center of core CO.42 cue t: hi3ner flu. at center of core. [0.s3

.

b.

Dr opted av :ttelf [0.4

c :.. c to reducec effectiveness is5roow:n3)

4

caused by ac; scent recs curing a s c r a 1.

CO.63

c. Contial r c:' E >. 4: s oce AP 5 F: :. c : s c e se:t3on i; o n '. y p. t r - of

red. [0.63

Fs,-

U Y, e N Y L

--

LY

wr

b e a b C T'

E'hyS1C3

r-

'~ 14C**

1

-

_

__,

._

-

--

- - - - , .

._

.

'

.

,

1.

FFINCI:LES OF NUCLEAR POWER F LANT GPER ATION,

PAGE

6

THERn0 DYNAMIC $.

HEAT TRANSFEE AND FLUID FLOW

ANSWERS -- inI-1

-85e12/10-DUCLEr

ANSWER

1.11

(5.05)

A.

The eucess. steam flow causes Tsve to decrease and insert

positive reactivity.

Ine pcsitive reactivity increase causes

=' eve- Incr ec s irog r a te.

W h e r.

the :Ica+

cuer tc risc

3+

reeches the PDAH, the fuel t en.per atur e rise will add negative

reactivity via the doppler feecback anc acc reactor heat to

stop the tempe*sture decrease.

The power iIse E n c'

c c.o l o c u n

will continue until reacter power equals steam cemand.

st.5*

E: . The rste st which power r.ses will be n.uch highet anc the

tin e tc r c 6 c ?-

the FCAn wil; be much s n a r t, e r because th-

Et f f

is smaller a r. d the rate st which reactivity is Ir.tr oduc et is

lanser (more nc3att.c

~~C:.

At the

+nc,

poact will b the

s a n.e but tes3per ttu e mucn higher (more n e 3 c t :. v e

P. T ~ )

t. u t still

.

ric - I c a c

.4.e.

1.-.

ce,cw

c

.

a

REFERENCE

ANG 1 Fescto- Thecr. part 1

p3 27

t

n k, u- . . F

...-

sc-se

.

. , . ,

ec

.a

A.

Th I . .t ci c:11 dic cs!,c,C:.5: Tc w1;l increase.:G.42 -cti

1: to

a. c: 1. . '. s i r.

e r.e r g y (hett) :. a l a r. e e . 5: r dT.CO.53

E.

ree1 ?Ica w11i

Lajus'.ea b,

ICS to a.41n'. Sin Tc's equal.[0.5: ';

C ~ 5 ',

-

will nave increasec feed flow anc

'E'

CTSG will have cec r essed feed

t' .. a u . t ,s , ., ,2

iL.>.

w.

r. sco

,.

.- .

.

,ca

.

A i n t ,, s !

lev (,

.

i

.

C.

CT5G iesel wil: ft.1;c

ieed flow t t: thtt OT5G.[0.53

'A'

DT5G ie el will

increase ano

E'

OTSC level will decrease, again to aalar,ce Tc':.

0.5:

1

REFERENCE

i

C erater Tralr.irg nanual Vc1 III, Hest Eachcnger Heat Transfer p 153

P

,

l

.

- - , - - - , - _ - - - - _ _ . _ - _ - - , . . . -,

- ,_ . . , . -

., _ - -

- - , - -

..

- . _ , .

_

._._

_ . _ . _ - . _

-

.__

__

.

__.

-

.

'

.

.

d

.

TEST CROS5 REFERENCE

F' A T E

GUESTION

VALUE

REFERENCE

01.01

.M

DJD0001007

01.02

1.50

0U0000*.006

Ci.03

1-00

DUD:.c;1002

01.04

1.00

DUD 00C1010

01.05

2.00

DUD 0001011

'

01.06

0.00

000000101

01.07

2.00

CUD 00010:0

01.05

2.50

DUD 0001014

01.09

3.00

0U00001015

01.10

3.0C

D U D 00 0101.3

01.11

5.00

D00000:017

01.12

3.50

C' DOC 0101G

J

'

5.00

Ome---

25.0(

,

.

. .

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. .

.

i-

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rin et/i g G m m r5lb ny

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Text

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