ML20138B660

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Exam Rept 50-289/85-19 on 851031.Exam Results:Candidate Passed Section 1 of Retake Exam & Was Issued License
ML20138B660
Person / Time
Site: Three Mile Island Constellation icon.png
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:
References
50-289-85-19, NUDOCS 8512120352
Download: ML20138B660 (12)


See also: IR 05000289/1985019

Text

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O.S. NUCLEAR REGULATORY COMMISSION REGION I

4

OPERATOR LICENSING EXAMINATION REPORT

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EXAMINATION REPORT NO. 50-289/85-19 t

< FACILITY DOCKET NO. 50-289

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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 ,

i 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: .[ M v ff

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S. Kister, Ctfisf, Projects Branch No.1 ' date

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i SUMMARY:.

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

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

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8512120352~051204

l. PDR ADOCK 05000289 '

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REPORT DETAILS

TYPE OF EXAMS: Replacement X

EXAM RESULTS:

I RO l

l Pass / Fail l

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l Written Exam l 1/0 I

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l I I

I Oral Exam l 0/0 l

I I I

I I l

l Simulator Exam l 0/0 l

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1 1 I

I Overall l 1/0 l

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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

-.

NASTY

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Attachment 1

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= _ _ _ _ _ __ . ___ . _ _ _ _ . _ _ _ _ _ _ _ _ . . _ _ . _ . . . _ _ . . _ _ _ . _ _.

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4 .

  • 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?

j TEhF. FREES. :r.:s,

2 a. 540 1000

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. e c.

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c. 665 2000

v. . et ,. .v - .46,, .3

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! PUEETICN 1.02 (1.50)

Critiesi H.st F;u 'um> ts cetinc3 s; the heat fla

a',whica

,eparture

s ,r oc N x i ea tc- .t.

.

3.in3 (DND

c : . o c c .ir s . Ft e r. .t, n, F :. . . .% t.- i r.

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... 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

i c 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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i (****x CATEG0FY 01 CONTINUED ON NEXT PACE *****> I

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--.,..-+->--e- - = . .--=w,-ww. -r*%.c.3-,.

,-- .-y. - . - _ _ _ _----y = - - - -,- y---,-my-,_,-,,.,3-e.-m-.-~3ye.-=---,m ,,,-e..=c- .w. -

= _ _ _ - . _ _ . _ _ - -

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1 FRINCIPLE5 0F N U C L E M. F0WER FLANT OPERAT!DN. 'A;E 5

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


e

.

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 . ,

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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

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u u t.c i t u d . . c, <

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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,Jr, a- .ilu

. ., t.. . . . .

i.co

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_

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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) . . i

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.

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(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


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LU tS..Gb, 41

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. 10 t o . v u, ,

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,

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t. U E .C *iTD r '

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1..*.*. ,.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

. .

a. E X.r- . , e n. . s una, c

.appent to resetcr pcuer sno . .s ( .

(A;Eu-e l'.e 1;;i;- .I m :.: e r r.c 0 s i s t e ; > a; E. L r r. . r. : e c :; c.

trip cccorsJ

c'. Assure tae s s .T. c tr2.;;=at accurs st ECL. EU L Al . sr  ; ; * f .. r e r. c e s

'

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 :- .

- 4 - --

,.A, , 1sw

-- - +$ e. u, *a* s s - w e 9 -

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 c crsmsters cuting the tra. sten.

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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


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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

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4

!

a. ,ncresse.

A

!

b. Decresss. - .

C. ,DCrE530.

A [ c. e .J.ew 'C I . 1 . ~- . '

REFERENCE

4

,Jestinghcuse .,erati

in

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s c l e r. c e ,.

.

en. ..,

.. pp ,-a; e,.c.

.-..

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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. 8

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se e00

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n to. .wtr ... 2 . s ,.

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t. CC .C its: .up r a t- ;3 n c r. - 1 r. c e r with res:, ity. CO.i]

1

AN5WEP 1.05 (;.c3;

K1 = le 1 + $0h* CO.6]

- . . _ ,

- .. . . . ..

- ,

_ v . 7,1

-

C v. .-c,

K2 = le 1 + 0.04

= 0.fo: CO.23 i

CR1 / CR2 = 1 - K2 / 1 - M1- . [0.63

>

C p. .. . e,1 u. _ hr ..

.

,f ,

. _ L, , -.,.

= 100 1 - 0.771 / 1 - 0.962) = S3 eps C 0 .' 4 3

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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 . ro. . -r t m

u-e

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

.

ANEWE F: 1.07 (2.00)

s

t

'ft

,

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

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

ens snoing : s pr es ente c.

'

. 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

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ANSWER 1.06  :.5;/

, . .

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

' cc ne : : s ; ,., ; / -: . ..

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

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

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

_ _ . .

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-

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 her EC.35: due to Xenon peak

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

- ,

c o u r. t rate ., a -  ::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 .

4

b. Dr opted av :ttelf [0.4 c :.. c to reducec effectiveness is5roow:n3)

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,-

LY U Y,wr eNYL

b e a b C T' E'hyS1C3 r- '~ 14C** 1

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

._ .

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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

cuer tc risc 3+ =' eve- Incr ec s irog r a te. W h e r. the
Ica+

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

ce,cw

.

. ric - I c a c .4.e. 1.-. c

a REFERENCE

ANG 1 Fescto- Thecr. part 1 p3 27

t

. , . ,

n. k, u-ec

..F .

...- .a sc-se

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

,.

iL.>. w. r. sco ,ca

.- . .

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

.

. i lev (,. A i n t ,, s !

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

i

REFERENCE

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

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TEST CROS5 REFERENCE F' A T E

GUESTION VALUE REFERENCE


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