ML20138B660
ML20138B660 | |
Person / Time | |
---|---|
Site: | Three Mile Island ![]() |
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
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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
,
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
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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
l l l
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
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NASTY
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Attachment 1
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AF'P LIC AN T ' E SI";N AT UF E
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= _ _ _ _ _ __ . ___ . _ _ _ _ . _ _ _ _ _ _ _ _ . . _ _ . _ . . . _ _ . . _ _ _ . _ _.
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- 1. FRINCIPLEE OF NUCLEAR F0WER FLANT CPERATION,
________________________________________________
FAGE :
THERn00rNAn:C5. HEA1 TRANSFEF AND FLulD FLO'-
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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
,,
. 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 .
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- . 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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,-- .-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
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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 . ,
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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
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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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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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Iw i V e. - e, M 6 A d_ N * t' H o t *
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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,
o
t. U E .C *iTD r '
'
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
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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
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ANSWER I.02 :1.50
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a. ,ncresse.
A
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b. Decresss. - .
C. ,DCrE530.
A [ c. e .J.ew 'C I . 1 . ~- . '
REFERENCE
4
,Jestinghcuse .,erati
in
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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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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 ..
.
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. _ 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
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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.
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. 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
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Nuclear Fundanentals
. 1,
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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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01.02 1.50 0U0000*.006
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01.04 1.00 DUD 00C1010
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01.10 3.0C D U D 00 0101.3
01.11 5.00 D00000:017
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