IR 05000289/1985019
| 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) | |
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O.S. NUCLEAR REGULATORY COMMISSION REGION I
OPERATOR LICENSING EXAMINATION REPORT i
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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
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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 N ' date i
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, i
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8512120352~051204 PDR ADOCK 05000289 '
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REPORT DETAILS TYPE OF EXAMS: Replacement X EXAM RESULTS:
I RO l l Pass / Fail l l l l l Written Exam l 1/0 I l l l 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 l 1 I 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 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 revie See Attachment 2 for utility comment 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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- FRINCIPLEE OF NUCLEAR F0WER FLANT CPERATION,
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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 TEh FREE :r.:s, 2 ,,
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' 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- . .
3.in3 (DND c : . o c c .ir s . Ft e r. .t, n, F :. . . .% t.- i 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
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e s e t. paraneter seFct2tei/.
j Licit your ans-e- t: Ti.CF E A SE , DECREACEr cr 'EhAINS UNCr.ANGE Eetetc: L:: .a r.t i l ;,* F.a t e . Reactor Cec'snt T e n. : e r a t u r e .
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- . Rescter Ccc; ant Fressur C3 G 0.5 es] 1.5-
! G U E _ _. I u_ . v_ .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... .
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! GUEc....2sN: ..v- fl... 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
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2 stable Ecstr.1ve s'titup ra 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 i startup rate to :erc~ Euplai ,
i (****x CATEG0FY 01 CONTINUED ON NEXT PACE *****> I i
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1 FRINCIPLE5 0F N U C L E M. F0WER FLANT OPERAT!D '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
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t . i. ,, , 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 Wh, cces tre GT3C s t e a u. temperature decresse betwe.:n -
7C'; ano I S " " t cu- r "
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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 WH ,,.
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GUEITICH 1.C? (3.00) . . i HOW -cold the actual cr;'.ica, ecc paaltico varf f r c t.a e e s t l i:. -a t 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 -i fcr 1 t ,i : Lt; 5 hcur s efter tac + rp o .
. / The actuel bor on c one r r.t r ett o: 25 100 ppe. Iower t hin t he value uSec for tae EC EFFD is used in the'ECF instead of the actual 200 EFF 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 tu . .
(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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State which rod has the greatest INTEGRA~EO rod worth and EXPLAIN wn Treat each c o n.F 3 : 150n SeFBTEtely- A rod at the center cf the core comparea to a similst roc s' the e 3e c# t,e co c . 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 tri An Anial F0wer inaping Roc compared to c centrol ran, o
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Curir3 pc ,4: cp s t i c r. s t 2 5 '. - i t ,- three 3) reacter c o c i a r *. pat (RCF < I r. cpeist;an tne 1 ;.vi i r. F. ; F ,1ccp A; is stsite E r 1 *: f ; ) ::scuss *he tc. lowing c crsmsters cuting the tra. ste .
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isr**** ****** END OF EXAMINATION ***************i
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- 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) ,
,- 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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! ,ncress A
! Decress . ,DCrE53 A [ e .J.ew 'C I . 1 . ~- . '
REFERENCE
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AN5WEP 1.05 (;.c3; K1 = le 1 + $0h* CO.6]
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- . ,PRINCIliES :>
OF NUCLEAR F0WER PLANT OPERATIO FACE '
THERn0DrNAniCS, HEAT TRANSFER AND FLUIC FLOW
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-ANSWERS L THI-1 -55/10/10-CUDLEY
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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 level The greater the I to Xe ratio the longer it takes for,suffi: lent 1 te $tesy t o ), e such that equ;11driu 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
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ANEWE F: 1.07 (2.00)
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, 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 '
. t:f. CT S G temp e r a t.ut e de c r e. a s es cecause the amount cf supenheat
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'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
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ANSWER 1.06 :.5;/
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-tn, e rt , s, meccers lesa nt3ar.l.c anc car. e v e r< t u a ,i t e
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AE the LO'NrStcP he t5 U" ;ti e W *- s T.s 1 0 n rEnOvC5 t. G: Cn 1o*r tn1 CO' ,
/' This intrccuces pcsitivc reactivity because neutron a b s c r p t i c r. has been r edu:e 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 cor As bor on concerttr ation increeses, its positive reactivitv effect increates
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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
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- FRINCIFLES CF NUCLEAR FGWEE FLANT GFERATIGd, FAGE
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THERn00'rNAnICS, HEAT TRANSFER AND FLUID Fw0W
ANSWERS -- inI-1 -65/10/10-DUDLEY ANSWER 1.09 (3.00) Actual critical position will be hi3 her EC.35: due to Xenon peak after the trip. E0.43 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 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 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, ,
c o u r. t rate ., a - ::cor si ., .s.-.
REFERENCE ruclear F ur. c s .~.c r t a l 5
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. a. . ... Center of core CO.42 cue t: hi3ner flu. at center of core. [0.s3 .
4 Dr opted av :ttelf [ c :.. c to reducec effectiveness is5roow:n3)
caused by ac; scent recs curing a s c r a 1. CO.63 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
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- 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) The eucess. steam flow causes Tsve to decrease and insert positive reactivit Ine pcsitive reactivity increase causes
- cuer tc risc 3+ =' eve- Incr ec s irog r a t 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 ceman 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
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. ric - I c a c . .-. c a REFERENCE ANG 1 Fescto- Thecr. part 1 p3 27 t
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...- .a sc-se 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 e r.e r g y (hett) :. a l a r. e e . 5: r dT.CO.53 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
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. i lev (,. A i n t ,, s ! 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:
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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