ML20213F952
| ML20213F952 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/07/1986 |
| From: | Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Woody C FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 8611170258 | |
| Download: ML20213F952 (162) | |
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November 7, 1986 Docket Nos. 50-250, 50-251 License Nos. DPR-31, DPR-41 Florida Power and Light Company ATTN: Mr. C 0. Woody Group Vice President Nuclear Energy Department P. O. Box 14000 Juno Beach, FL 33408 Gentlemen:
SUBJECT:
TURKEY POINT EXAMINATION REPORT 250/0L-86-04 The NRC administered examinations on September 8-11, 1986, to employees of your company who had applied for licenses to operate the Turkey Point Nuclear Plant. At the conclusion of the written examination, a copy of the exam was left with your staff; at the conclusion of the site visit, preliminary findings on the operating examinations were discussed with those members of your staff identified in the Examination Report, Enclosure 1. Copies of the written examination questions and answer key are included in this report as Enclosure 2. Facility comments regarding the written examination are included in this report as Enclosure 3. In accordance with 10 CFR 2.790(a), a copy of this letter and its enclosures will be placed in NRC's Public Document Room. Should you have any questions concerning this letter, please contact us. Sincerely, (Original Signed by H.C. Dance for) David M. Verrelli, Chief Reactor Projects Branch 2 Division of Reactoc Pr.jects
Enclosures:
- 1. Exam Report 50-250/0L-86-04
- 2. R0/SRO Exam Questions & Answer Key
- 3. Facility Comments cc w/ enc 1: (See page 2)
O 8611170258 861107 ADOCK 05000250 ph ! PDR V PDR t}
y -_. I .. . , , , Florida Power and Light Company 2 November 7, 1986 cc w/enci 1: C. M. Wethy, Vice President Turkey Point Nuclear Plant C. J. Baker,. Plant Manager Turkey Point Nuclear Plant L. W. Bladow, Plant QA Superintendent J. Arias, Jr., Regulatory and Compliance Supervisor cc w/encls 1 & 3: Bill Waylett, Corporate Training Director cc w/encls 1, 2, & 3: Bill Miller, Site Training Director bec w/ encl 1: Project Manager, NRR State of Flcrida bcc w/encls 1, 2 & 3:
, Senior Resident Inspector Operator Licensing Branch, DHFT:NRR d Document Control Desk RII RII RII RII 40$
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7 [a ' lb. When you c o : p l e '. e your e:'< min a t ion r you shal;;
- e. Acsemble your e x a s.i n c t i o r as " allows:
(11 bam quest on3 i on top. (2) E::an aidt - figures, tables, etc. (3) Answer I >cres w includin-:- 1 J' u r e s which are toart of the a r. s w e r .
- b. Turn in your copy of the e , e ". i n c t i o n and 211 pays used to answer the e : a r i r. e t i o n questions.
- c. Turn n 1 11 screp prper and the balence o# the paper ^het you did _
n o ^. use for an werina w the c.uestions,
- d. Leeve the enac.inction cree, as defined by LSo resniner. I' cfter leaviner you see #ound in this area while the enamin-: tion is stil:
in progiestr your licence may be denied c- revoked. I I l 4 l I l
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s Which :e; of .oarameters below :oe s t describes cent'ifugal r.s u s r> t r u n c '_. t conditions?
- a. Wic,h : 1 2 c h a r.: e .cres ira, w icw flow, hi;h oower . de v e
- b. "C -
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- c. Lau d.2 charaew creswr >, hiah #10wr hi;h ooper dem2nd s i
- d. 'ow ::scharge p " e ,_ .'r e . r'.igh flow. 'ra power dement n . _. c a c' i s c u a r m. or e.avre. Icw l o w , hif, oower denand n.* o r. e.) T. T_ti.5 ne .5 .0o e. , . nssn '.
'J h i c h of the following curvas ee attached 1. J a c representing Menon contentrc* ion is correct "or L a :- given power liistory" Q Ls-ac o: ' .?. mn #. : ..O3 i. ?. . !) A 'i m t
A reac+ sr has hoon m eating - t. #ul' coune for
< *hrm. months when : manual reactor trip occurs. All sy: '
mt are ope r : t i er. -l and the simr dumps are . immediately p' aced in the s te 3a :;ressure control node. Ten minutes aftor the enactor ip, all RCPc 'ne trinoed. T went , minutet efte- the reactor trtpr uoop i RCP is , jogged m a c.. n t m r:1y. '4 h : - 3
=ot of trace. / 3 - d) on f:sure t 2 ~' ." .. a s t closely rer"enents the prc 't '. deseribed event ~0 QUESTION 1.03 (1.00)
For e 3 cli of the f' c l o w i n oa ..: a r ns ' - 3 comoare - Core T h i m 'a l e e l l *o n
. a N o r m: 1 Core Ce'l and Indicete which o f' the t cc has the higher value I. r u t . d c o o r' ; t : a n s , avera;e w sclues) i
- 1. Total pou-- ,e.- r o d u c t i o n M %
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- 1. PRINCIPLES OF NUCLEAR POWER PLANT CPERATICN. PAGE 3
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HER5UDIk555C5~~HEd I EEU5E5E~Iflb~f[U56~EEUU GUESTION 1.05 (1.00) During a reactor startup, equal increnents of reactivity are added and the count rate is allowed to r e r. " h equilibrio: each time. Choose the bracketed ( C]) word (s) that describe what is abserved on the Source Range recorder and/or SUR meter.
- a. The change in equiliorium count rate is Elarger] Ethe same: Esnaller2 each time.
- b. The time required to reach equilibrium is :langer] Ethe same] : shorter 2 each tine.
QUESTION 1.06 '2.00) If steam goes through a throttling process, indicate w, ether de followins p rametert will INCREASE. DECREASE, or REHAIN THE SAME.
- 3. Enthalpy (0.5)
- b. Pressure (0.5)
- c. Entropy (0.5)
- d. Tenperature (0.5)
DUE3 TION 1.07 ( .50) MUE or FALSr.* Ouring cold plant conditicos, you would enpect the COLO celibrated P U' level inctrument tc indicate WIGHER thn- the HCT c a l i b r a +. e d level instru+er'. QUESTION 1.00 ( .00) Attached are curves for overall p o u e de'e: md Doppler on.y oower defect indicating Lath EOL cod SQL - :. : v e t #o- 2 cycle 1 core. 'Su _ show Doppler l dOf2ct beCCnes les- ,esetive oue: core 1:ee. a h ., tren eoe. ..e overal. PoWor defCCt beC019 more nefit.Ve3 l c um C Artcat- ci con 11sut:) ca En ucE .orv-i 1 l l l l l l l l
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THERMODYNAMICSr HEAT TRANSFEF AND CLUID FLOW DUESTION 1.09 (2.00) Unit 3 has ,, n t restartec fc11cuina a refuelina w a autace while Un:t 0 is w nect EOL. Antwer the fc11cw:n3 regardins the differencer in plant respence between the two units (explain your answers); c) At c steed" neue- ' leve af 10EE(-8) a m re s durinq e startup, ecus ! reactivity additions are made (appronibately 100 pen). WhicN Unit will hcv: the higher steady state startup rate? b) At 5 07. , c t. e r , a centrol rce(100 pen) drop _.. Assuming NO CUNBACK or , ODERAT0; SCTION, which Unit util have the higher steady ; tate Tavs? t et 4 Q.ll O> T~- T n. a s. 1. O. ( *. . E. G ) A reactor which has been operating at full power (EOL) trips due to a Loss ; of All Offs:te Power. Natural ci culation canditions have been established and s '. e a dung to condenser is operational. Steam Generator levelc/prec- , r suces are et no-load etable values. Core d e t e v. heat generation hewever, i j i ., exceeding the frce convect;cr. .-:a+ 'rans#er rate ccPabillty. , EXPLAIN i the thermodyncmic prine:ples whi : > 1; c a u :, e fuel element toepcretures to ever,tually reduce to lower v a l u t. 3 , (acsume a relatively constant r t heat aenerction o rate within the fuel) i i l i 4 ! l r.p.ira e1 r. t n y 4 t.31 /1..QOs ! i i > l Refer to figure 43'54. EXPLAIN why the change *2 the differer'. .. i prescure . decreates c the valve is opened. Comparing riping se3nents -P2) to l (on_ _ oc_). QUESTION 1.12- (1.00) i
'R e s t r i c t i c ~ an F(0)(T) limit include penalt:e2 cue to unccser and reficed rates, c o s t - L O C .^ . GIVE one itc,* bacic #or core height -es4 -ictions ;
ch rfD)(T) MD mplain whert and why it is esstrictiv . ! l , r i i i l (ttn* CATEGCRv O' CONTINUED ON F. X T PAGE n**+ l I i. l l l ' 1 . f
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- 2. 9 THERMC0YNAMICS, HEAT TRAN5;ER AND C!.UID CLOW D'dcc4a T n .ri .i . s 3 <,e,en-> uu Cefer to ficuro a 1 357, 'rayq ys, w
- eyep a and a n s .4 e r the fallaw n", w
- a. On the g r = ,c h curve A' bounds the m e ::i n u r ope r c4 1ng loop tempercture at a 3:vem syst.em precav"e for a p a r t ;. c u l a r reactor power. E::P lain the b2:11 'c- araoh . 'A' Pnd Mr 11 has z ne a t-Ive vlooe. ,
- b. 0 sph 'O' ensoros that two adserse conditr a are not r2eded. S t a t m.
these two conditions,
- c. EMplain i i y' curve '
C' ic valid at 155' ryality and not at 15% 12.v a l i t y i OUESTION :,:c (2.50' With regard to the s y m.p t o m s of : small breai _0 A r steam 1. i e 'oreak anc b s i A -
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- 2. E::p l a i n why ;' r e s s u r i a e r level decreaces on each of these t :n,ients.t.PJ L
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I THERMODYNAMICS, WEAT TRANSFER AND CLUID FLOW I J QUESTION 1 16 (2.00) j Explain two reasons why the conputed moder=ter-only power defcet under-estic.cter the actual defect- due to redirtr ibution et BOL- assu~ing s calculational value of MTC of -a peo/deg.F. C H F C' 7 C5 = 1200 ppn] i OUccTrnN-
- . 17
. ( '. . n o, i.
t r vplain how differential coron worth changes with increasing baron concentration. Include in your cnswer whe* her DBU increases / decreases / remains the saw and why It does sc. i OUESTION 1.10 (2.00) i EXPLAIN the two bases for control red bank overlap. QUESTION 1.10 (2.00) Refer to figure t 363, discuss the two factors which effect the A :: 121
- Powar Distribution ct EOL cnd result in c reletively flat peuer
- distribution. .
1 QUESTION 1.20 (2.50? For EACH of the following sois of conditions U P'_ AIN w h i c i' one would result in the cre lest reactivity chsnse due to centrol rod insertion. Note, A;sume 100% power, Bank 0 at 220 steps, 30L.
- c. An cret cf :u g h relztive Plu: vs. low relative flu; .
I, e
- b. Edse of the core vs. middle of the core, k c. Rod 11 (interled) vs. red 42 inserted beride rod 11.
i 4 1 J (st m CATECOR' 01 CONTI4 LIED C .M SEYT PAGE .* m .t ) i 1 J l l > t t 4 1 5 l h 1 i 1 < i 1 vw=.m'm-- v--r-mwwww*.,
. i I
- 1. PRINCIPLES OF NLICLEAR DOWER PLANT CPERATIONr ~ ACE 7
THEPMCDYNAMICS, PEAT TRANSFER '4ND FLUID Flu ki GUESTION 1.21 (1.50) In response to ES-0,2 Natural Circulation Crold wn, it is directed that the RCS be borated to Cold Shutdcun concentretion prior to RCE coc1doun. This action res';its in an over-beration of the ACTIVE (core +1oop) Portions of the cysten, considering this, answer the following 3uestient:
- a. Why is this action necessary during Natural Circulation Ccnditions?( 75)
- b. Why is thic cetion nececcery prior to RCS depressurization' (.75) f (FTtVA END OF CATEGORY 01 (T***)
l l l l l l l r f
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4 - 4 .- -;-L-.. I,
- 2. PLANT DESIGN INCLUDING 5AFETY AND EMERCENCY SYSTEMS OACE O QUESTION 2.01 (1.00)
Which of the following is NOT c scuree o* water to the PRT?
- a. Reactor Vessel F1:rse Leakoff Detector Drain
- b. Letdown Relief V'lve RV-203
- c. RCP Seal Water Return Line Relief Valve RV-382 t
- d. Safety Injection Test Line Relle' Velve RV-859 I
OUESTION 2.02 (1.00) ( Refer to figures te02.1 and 402.2 clow Paths Du-ing raakeup Modes. Which one of the flow paths (A-D) corroctly outlinar the Alternate 0: 1ute mode o* l operation? DUESTION 2.03 (1.00) Which of 'he t' o l l o w i % statements correctly describes the o 'i R System linevo
, when HOT LEG RECIRCULATION :: established? (assume both traint of RER cre I available) 1,
- a. Eoth trains are used to supn1"i het leg recirculat:or e :e c l u s i v e l s, ,
- b. One l,r n n is used to supply het 1c3 recirculatior cnd the other train .3 usec to cont:no cold les recLrculation.
c, Doth 1 ains supply v2th hot and cold 103 "ccire s i n u l t e r,t a u t l y ,
- d. One train is used for hot lea a recirc =od the other _ :.n is to u t in :tendby (ie. *ee:Tculates fro 1 N :'X e r outlet sc :HR pump
. I 1s-
< > & s) .
4*wv* CATECORY v2 cc)NTINUED ON 'EX' OAGE **'*(* ~ l
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_________ _ .. ____- UnT m.m______ _______ ___________ _________ 'l i QUESTICr' 2.04 00) Which cf the followina,., flowpaths describinq has oewer is normally . supplied te a typical vits; i nstrument but i s correct?
. u,. n. 'M, C fa. m_ m. o. '. +., u> .1 h mt . r. o. r ' _ # i o. ri . t. o , -
- U. nsr ., i n. . v. a, n iv._. - r_t t_ o_
120 VACr :nd supplied to 2nrtrument bus.
- b. 400 VAC '
rom vital tusr transfor m *c 120 VAC, 2nd con,slied . l tc instrument b u t. .
- c. 125 9C r o m batte y, supplied to b .' t e r y aucr i nserted 4
t, o 220 VAC. and tu.o.olieo to nctrme ;t bus.
- d. 480 WC f"oc sital bus, entified to 120 VDC, 2nd sup, lied te Inst unent bus.
OUESTION 2 . %- (1.00' i W h 4 m. -' '
,he r. o '. '. m u '. '. J - 2+mu, + e .c c , i s, .
+
2 u n c_. o_ r n ' v. g * -
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- of toponent cooling weter RC
- thermal berrie- flc , it correct?
i
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- r .* C A T E G ' R ': 02 CONTINUEO l' N NEXT P /1 G E *.* * + 1 :
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- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY S Y S T E riS SAGE 10 GUESTION 2.07 (1.00)
What is the purpose of the following precautions associated with operation of the Reactor Coolant Pumps' a) Do not open 11 Seal Leakoff isolation valves until RCS pressure is 3 rester than 100 psis. (0.5) b) Do not open il Seal Sypass valves until t1 Seal Leakoff valves are open with 50 psid s c r a t. s t seal. (0.5) DUESTION 2.08 (1.00) Fill in the blanks in the statement below ressrding the Standby Steam Generator Feeduater Pumps (SECFo)* Des: des being vued during st2rtup and shutdcwn, the ESCFPs are also used c; : (n) . These pumps are located adjacent to the __________ tank and take a suc+. on on the _,_________ t;ne. Flow to the P/Gt it controlled by the _ _ _ _ _ _ _ _ , , , vc1ve(s). QUESlION 2.00 ( 1.10 ) The following questtons deal ,.t> the Intene Eccling Water Systcm (ICWS).
- a. What ere the THREE l o c ch cupplied by t% ICWS? Do NOT 1ro_lude redundant loads. (0.5)
- b. What vc1ve in the ICW3 : e cirectly effected by 2 sc retu injection signal? Include in ycur answerr _c u and w?"; it is ef'ected. (1.0) 1 1
l 5 i l GUES' ION 2.10 (1.00) i List a sets of ECCs related vs!, - required +c c t; _ ,*e
. 2 'CCA which l
heve their control power bre:Eer_ caked c u '. cur :n; .t:c21 operations.
***T* CATEGORY 0: CONTINUEL TN '+ EXT ?ACI ****v) i i
ve -- v' -
,s. _ e e w-, wom -tvs.m e sw s -e -e w aw wwwa -
4 4I i 4 o_ . o$ ANT
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- o. U we c v T.Ds-c o.4r
- .3 <4 .en>
List the 6 e s s e n t :. a l safety related l o .i d ; served by the Ca ; .onen . Cocling Water Syntet (redundant con anent: like CCW heet e:m h a n s e r : 're one load). O U c ac *r a. v ns. u.,,
- e . ,eO) a
- a. Pefer to f igurec (397.1 and t'o7.2 Pesctor Coolant Punp s. _ .i s t all a,
s r
- or' .c d. .c. th, i c h. ~. . . i.ir +. % me. '" -t u' " +. a ns n4.'.
. ,4'+
r - ..r. . .em < m o'3 . to.e' a
- b. RCf 3A 7 tart sequence is in progress (i.e. O '. P control switch to neutral end OLF breaker closed) with 400 csi. all oressure.
4 r Prior tc the e"otration r of the 120 see t:ner the signal *
*cn '
and" gau i f ;. :.11 open t i
< n. e-4- i .au , m, ,. ' n > >. . c .ym ,. c, n. 4 S. e n. e c ,i: +' r+.. .' . # n ". o r.
-.. . *u h n. c o ... c' '. o_ ' ' n m, M_ . # 5 m.
RCP start wquence. ' 1. 9 2 l Q {ml 7 C> '"rT m Q p, 9.
- O. . (4..Ca s, t'
)
I
- a. ': e + '
to f1;ure 4300 4 eater o cuer 2:.ct th',1cn. 'i t a t. e +,he nurpose of c A L, - r' u . r u, n +s , .- - , ,a /sur'. T, em, a ~Er. t*sc v , C ', 4-u- ,,.m1 i ; ,, n , e~m. o. - ec-r. - - - - 7, ium: v . i ,,,s.,.y c. , w ie v , - ,
'reev -' -
i 4
- h. How are mall electrical grounds (e.g. s rounds which do r. a t t r :. ?
b r e a P.e r ; ; detected /innicc*,od on Pressurl e: Fetter stringc
- c. 'J a w :. s a bus stripping signal to 3 a c k u ,r Hcater Group 9 c messur.cer i h e a t. e r s over t 1 dero (incluci location o *~ contrcls)
QUESTION - ' , 14 ' 1.00) 1 J. E::P ldin the pur pO' d fOr 'i a v i r. ] the 'J' r. c ." Z i t_ _ .n 'ha #eedWJ 6 0' d . . e. 5, r .4 %. >.t v A 4 ,n li r..-r,..-
.=0
- 7. .,c_ . r '. v, .ii + n n_ Hs - '*
p 1.i r p 0, 2 3 s4 i, %.1 ; - 1 .- . ._fp- ,e: r k.3 . .
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- j s n. . c* ,
.; --i-'-eru'r - 'e ' :---
a o ps p v. s v .,,+ n- e, - r4wp..-..., s .a e'CW ^ " u? .^n "src. ~. *.
- P. "
J fIr. C a rYf.
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flow i.- O t il E f Vid dTIVe Ile _1 E :Ch DOG" J c' C U r '. . A s s U ', - ; r, q tSr nur- ;g 4 . I d. .4 ~4 . J r . e, = *ae se b 5 M* tie. u f1 w" D gfa..] , jf9
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( yy2yg r nST. r q n ;' v G. ^. " nv y, T T.. N ! ' *. % ae n aj NCYi ' S parc. gg3y2' r
. - - . - - - - , . . - . - - - . - . - . ~ . - . . - _ . . - . - - - . _ . . . - . . , - - - .-- , - .- -
i i l , 1 _, c, . , w T. n_, e . T. C N. c^ mn m_ y ,-4 N. n. r_ y r o r.,"cTt s oYcTrH.e a a . o, A.a_rr _1_9 _ _ _ _ _ _ _ _ _ _ _ "_ _ _ _ _ ' N r, '_ U r.a N. r_.___.___________________~_.____"u,__________ 4 GUESTION 2,16 ( .50) Refer to figure 4401 Chargins Fum, 3. STATE the force (s) which ,cintain i seci uater flow through the packins o# the charging Pumps. 4 l QUESTION 2,17 (1.00) 4 Refer to figure 1403 NIS oower Supply. On an operating unit the inverter to 3M7 het been transferred '_- c INV AS froc INV 3A. Prior to the transfer INV AS output voltage us greater than that of INV 3Ar E X C"_ f I N why this i higher volttae s would have no effeet on the aceration of the 'ower Renge 6 ,._ l N1 in:trument Fower, t QUESTION 2,1? (1,50) l a. If EDG "A' is tied onto the 4KV bus w i t r. greater than nin1x leading i and the c ,u e r ; t e r niece the DG voltage cd
, s u:: cwitch in the reite' direction causing DG current to decree c- would the machirm be operating in the lead or Ias code' E0,52
- b. By ;;ing figurec
- 191.1 and 101. 2 d e t e r --i ne 2ny a c t :. o n s 2 cut . 2elt 4, on 3A f 3E woult beve on the EDG includin; ctart/stos, of EDC and :0,52 b* e ra' er interlocks. (acsume all control suttche; are in normal o o -: :. + t o n )
4
- c. Whct is the c o n s e c,u e n c e s. c" c fa:!ure o' the soak tece 0: 1 ovmo durino 4 3 w i EOG s 'r> e e d reduction from tsted : Peed to chutdcwn c o n e :. t i o r s ? ' 0 , 5 ]
i a 1 4 1 i: t r y n C c- T E G O P
- 02 CONTINUE? 09 MEXT c' ACE xx m i
-.__- - . . . - ~ - - - - - - .-
a !a i! - P t e, u p i vsu
. . . r. De.erry ~s ry.. Ce u- uw..v, c-gr-<
- - n.
+w n r e r u-r y~ v. c y mt r e. \ - o wre 4 -)
.a L (
i ' i QUESTICN 2.17 (2.00)
, For each of the following abnormal p l a n +. conditions state whether ar not
, AFW pump 3A would inject nto the St+_an Generators at rated conditions AND , for each condition :nwhich the AFWP c'oes inject state all adverse conwguences u r the given conditico (assume a val d start signal occurs). Consider each ccse seperately. j a. The discharge flow transmitter on AcWP 'A' has a failed "".ich" high
- prescure tap.(prior to rtert)
! 5. SG 3? supply to Train i f. valve 3-1004) fails closed. i
- c. AFWP 3A Trio E Throttle vrlve trit rolenoid e i has sn open circo
- t.
J !. d. AFWP 2A Trip & Throttle . alve connectina "cd :orinc :. ; _ . ached # rom . i the red. s ! e. The main oil pump shaft fails. 1 I j m_i r_. c. T I O N. . .'. "'_O ($. . "a O 5 4 j a. Nb Ch SySteN CVpp11OC tNO w3t9" 1OW CP thO $COr]cncy ContJinZCnI t Filter System (ECr5) dousin';
- 4
- b. Once air ficw has b e s> n restored to the iCIS ic it possible to shutdown I the dousinq 0
, - s v. s t e m -f r o r the control r 0 0 ~:
t
. a. I . J es h k k A e Conditions WOuld Occur dUring f!n operatier. DE a reEult O # th9 LOOF ceal being drained'?
p.urr,Inr ai u s
-' o*
-. ( <. . rJ o s, The Overpressure ditig ation Sys*,em Tect: 2pec; re;uires ,ha t MGV-043 A!5 l (CII Cut 1etE) a n ti P10 V 06d AFr (Hot e3 Iri, . e t ; o n ) be verified m '~ 0 8
' daily when OCS temperature is '380 dea, ~ Wha', L: tho has 'e- 'his 4
BCv1Cn-1 4
.
- u' t. - , .
- . . _ - f. 9. , . . . .
i i Refer tO #igure 4409 '9asic CVC5 F10W 00.:nCO*. '~ 7P OQlntc I - ' state the 4 i i d (* $ 1 'wSb vO Ves OI lUW .s' iC1 U" eaC lb El 9 1 [ t t , i
)
1 I ( A a # :s a (A'{ COL 32 .,' O y ' T N U { D ][j NEX* OAC[ rttvgi i I. t J r P
=,e,=
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i
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS PAGE 14 !
J QUESTION 2.23 (2.00) List and explain two different types of edundant protection schenes employed _te prevent depressurization of the RCS throush a feiled open Pressuriner PORV caused by a single component failure. QUESTION 2.24 (1.50) a) What are the 2 cources of Dorated water available for the Spent Cuel I Fool? (0.5) u) What 2 design features of the spent fuel racks ensure criticality does not occur in the Spent Fuel Paolo (1.0) QUESTION 2.25 (1.00) ; If th" O cuer Range ' ROD DROP AUTO TUR2INE RUNE'ACM" is bypaccede what conditient must e x :. s t and whct s y s t e :n will i n i t :. a t e I turbine runback' t r t t
'r**<* END OF C AT E G 0 c:Y 02 *****)
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GUESTION 2.01 (1.00) Of the fellowing signals that de-energize the diesel " Ready To Start
- light, which is cico interlocked tc prevent the c'iesel fran stcrting?
- a. Low Starting Air Pressure i-
; b. K e '/ Switch in Bypess
- c. Low Skid Tank 8..e v e l
! d. Lou Prelvbe Oil Pressure f
- e. Low Prelvbe Oil Temperature QUESTION 3 . 0 'i (1.00)
At 100% powerr with the steam dump contral s y s t e ', in the Tev; moder a 10% step loss of load occurs.. Assuming no reactor trip occurst the condenner is ava:.labler and the reactor operator manuelly operates the control rods, which of the following would occur if Dari 1 (CV-2827 end CV-2928) steam dump valves failed to open o
- a. Bank 2 (CV-2029 & CV-2830) would open.
! b. Atmospherit dumps .sould oPen,
- c. 5/G tefeties would open.
- d. No o t,h e r ster valven would open.
QUESTION 3.03 (1.00) Which one of the following canditions uill result in a reactor trip?
- c. Lou flow on 2/3 detectors i r: 1/3 1capc when c' - 7 anc R-8.
1 b. Lou # 10w on 2/3 detectors in 1/3 loops when o-9.
- c. Lou flow on 1/2 detectors i r. 2/3 loops when P-7 and P-0
- d. Low flow an 1/3 detectarc in 2/2 Icop- when 6-P.
4 1 (***** CATECORY 03 CONTINUED 0" NEXT c' A G E *trt*) I 1 d 4 i 4 1
- , , - - ~ . - - v, - - - - ---- _-, ,,,-,,,- ,n m,,,n.,,w,- ,,-..,n,,,.n-,,n__.,,-.n _ _ _ ~ . . mwn,,,m- n,,,-, n.n_--,- - , , - , - , - - , - . . , . . . . . -
s i i
- 3. INSTRUMENTS AND CON"0LS PAGE 16 OUESTION 3.04 I.1, 0 ') )
Indicate whether the u l l o w i n g situations would caus- the steam dump system i tc AP" ONLY, ARM !, ACTUATE or HAVE NO FrrECT: a) RT-447 (1st s*. age :. t ? v l s e prossure for load aeject signal) fails LOW, Mode Control in Tsv3 mode. Tre# Tav3 by 6 des F. b) Turbine '-ips, Mode Control in Tave mode. Loop A Tave fails HIGH, the Steam Dug Control Reset suitch 1E HELD in the 'Bypesr* position GUESTION 3.05 /1.50) Answer TRUE or FALSE to the following.
- a. With no rod not:.cn in progress anj the rods in Manual, the rod speed n, e t e r on the control bocrd inticates a speed of 0 s: p m .
- b. The bank overlap unit will ONLt count steps ;" the red control bank
- t. elector switch is in AUTO or MANUAL.
c, Only cne of the three ' movable, stationary, or lift) ceils of the CRDM is energized at sny one tine. GUESTION 3.06 f1.50) Indicate whether the following will cause a Rod Control System U? GENT or Note-URCENT FAILURr 'erm. j a) Loss of Main 100 VDC o ever in the Logic Cdinet b) Sleve Cycler fails tc start count:ng upon eceipi cf 'Oc' pulset c) Loose circuit card i. n the Fower Cabine 4 I 1 I I I L. (***** CATEGDP' 02 C 0 t:TINUED ON NEXT FACE n*v*'
t i
- '3. INSTRUMENTS AND CONTROLS PAGE 17 GUESTION 3.07 (1.50) j A n s.w e r the following questiont regarding ESFAS TRUE or CALSE
a) In order to generate a 'F' signale 2 out of 3 Hi Containnent. Pressure OR 2 out of 3 Hi-Hi Containment Pressure signals are required. 3 b) The S/G Delta P 'S' signal actuates when 2 out of 3 S/G pressure
! detectors for 1-S/G are 100 Psi GREATER than 2 out of 3 Stean Line Pressure detectors.
~ c) A Reactor T rip :n coincidence with a Low Tavs will esult in Main Feed l Water control valve closure, but the hein Feed Water pumps will still be running if they were operating at the time of the "eactor trip. e i ) QUESTION 3.08 (2.00) i hatch the interlock descriptionc in Coluren A with the appropriate logic regiiired to cause rod withdrawal to be blocked in Columr B. (coluen B items may be used more thari once) j COLUMN A COLUMN 9 c) Power Range High clu- ? 103% power 1. 1/2 + 6 n. n/n. i b) Overtemperature Delta T rod stop 3. 1/3 , a. 2/3
; c) Irtermediate Renee H: 3h Flu: 'i . 1/4
- o. c ,r a 7
d} Power Range Rod Drop 3/4 i GUESTION 3.09 (1.50) For each set of o,lant conditions I:sted below STATE all N ict:.ons i (of 1,2 and/or 3) which would be generating c ecd n ovement E.ignc1 and STATE the respcnse of 9an9 D rods (in, out, r. c novement) to this signal, j Bank 0 et 200 steps. j 1. Dani. Gelector Sw. 2. IN-0UT-HOLD lever 3. Plant Condition
- 3. Manual IN Urjent "ailure
- b. 'D' HO' n "re' fo:Is high i
- c. AUTC 4GLD Tav3-Tref +4 des.F a
1 j (**r** CATEGORY 03 CONTINUED ON NEXT DACE ***vw) I, f I 1 a i
.- -, -, - -. - _ - - _ . _ - ..-,,_ -_ - ., . _ _ . - - , - _ - , - n,..-.._,
i
- 3. INSTRUMENTS A N ') CONTROLS c' AGE le 4
g.yrc.T.T.ON.
- 'e , *^
1 ., (,1* . A O ). I l List ALL of the signals that will cause Mein Steam Line Isolation. Set- t points, not required. j r 0 t;. , 4 Q U r_ e.a- ~1. a. . r, 1.,no., 1 r List ALL the interlocks that nust be met before the RHR suction .solatici valves (MOV-750 ? 751) con be opened. 1 Q U- r m.,i 0 N 'l..'.
. ('. 0. 0. )
Refer -a figure 4420
- Emergency Containment Cocier Far* and 2nswer the j foll,auing:
- 2. Fcr the matr,' casitionc . marksd 1 - 5 what .occition should the valve be :n for the civen control switch oasit:en'
- b. If the fan switch is in the S T 0 c' position and a sequencer star
- si:nal -
.; ic received, HOW should the fen, cutlet valve and :. r. e t / o u t l e t cypass s valves r e : a* a n d ? t i g u- e n T '1 O N. . 3. . . ( .* . "a A ,t
- For the CCW toeperature CV-2202 EXFLAIN how the input for tenpereture etntrol in AUTO is derived.
QUESTION 3.14 'l.00) i A L 5 u 'h E the follow 1DS CCW .uDD Q Cl;'On90ntE w O I.! Ul .b* b dbe IdC .e b bb' I.1 E pump is running j A ,o u n 4 < .a rCEGd gut 2 Tid Open O, If *9' D U o niD r 0 C 01 V F f a in DVOr Cu'"eht 100koUi W h C *. El$GU1(lJ W O v 10' CVtO j 3 tart 'C' pung AND at what tine would I' I i 3 r '. '
- b. Would the events i t, ':' ._beve be d: #fe*ent wi'h tho :oca1 4e ate cw;tch for 'C' in ' local
i 1 (***1x CATECORY CO CON' MUD O' *J E X T OACE <*'+*) I k. 4 1 b 1 1 I i
-- ,- , - - - - _ . - . - - _ - - _ . . _ .. ....__...._,.._.mm.v- ..,,- - -,-,- _ -.+-e-.,--
a .
- 2. INSTRUMENTS AND CONTROLS C' AGE 19 GUT _Jfl0N 3.15 (2.00)
- a. '~ o r the Unit 3 Rod Position Indication tRPI) pcwer supplyr describe the supply to the DC power system- including both normal inverter supply and alternate supply. Include all autonatic features ascociated with these two sources.
- b. The Rod Deviation Monitor generates a ' Rod in Motion' signal. EXPLAIN the basis for thic signal AND the actionic) which are iritiated by the signal.
QUESTION 3.16 (2.50)
- a. State all inputs into the Stean Generator Level / flew controller FC 478r in automatic.
- b. S e c t i- how does Steam Generator level flow controller FC 470 cperate the M ei , reedveter Control Velve? Include notive force (s) and signal co, tioning equipment.
- c. There are three olenoid operated vent valves associated with the MFWCVs with time rie ! a y e of 5 , 5 , r n ci 70 m s. STATE the initiating signcis for the valves AND whether the valves energize /deenergize to trip?
GUESTION 3.17 (2.50)
- a. The charging Pumps have two ' Low Speed Stop' settings. Discuss the modec of operation in which these ctops are applicable and how their values dif#er, b, ?e'or to figure 1425 'VCT' Holdup Tank Diverting Valve ( L C'J -i l 5 A ) ' .
EXPLAIN the ciencls which will operate SV 115?-1 and SV 115-2 in both the VCT and Avtc Divert positions. 3 i l l (xtr** CATEGORY 03 CONTINUED ON NEXT ;' A C E *****' l 1 l I I I
, . , , , - - . - , - - - . . _ . , . . . . - - , -_ _ . , , , - , . _ - . - - - _ - - , - - - _ , , - - . - - , - - - - - - _ ~ - - . - . , _ _ . . - - - . - _ . , . , . -
r
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. - + o ~ ., 1 r. ,.i+., " o_ ., ' - '. .'. o_ r .
level ch:nnt; i : LT 45?) : r .olerted. Answer the rg]1ay nn: -
- a. Wculd , :ommon stlure on LT 161 _. cir _T 462 causin3 _ ;t ', o resd r, o- . : ..u. . ,n_c,.,.,
+
s =, n, - 7 _. v. _ + n.. 46 ; -;> c. . ,x_ c_ i r. w, r c., - , H. T h e, e. o c. c r o_ . .c o - 1. ~_ g #ar ' '. E ?. ' n t- 7 5
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- a. n_ o4. w
- ,, , r 4, ..g..- *
., h o-
- r. e ' e r o. rem .-
.n- 'v~. J., r . - . . v< . i c + v 'u =- c' ' . 4So w - i ., n- <>u - -
..ne.1 c --
a i' f e c t nu LM Penwriter wi t ch would accur is - ;rn: ult ca f +he .
#~
3ilure,
- c. Lict : . '. func.lont 4 of Dru,cvr:rer DTs 455 -
45d
- d 457 gy cTT.on .
- 7. . ' o . t ' . "a 0 )
Refer to ' gut 32,1,.T: g jpg
). W h ., t. '
the ,iin o o s e of s
+v -h 'i e l e c t a r "w:+ _h ; awr ~ anae a A 4 n or wer-
- . pj} J t. ..(+ . , t, . n t . - , < +.. i. , i..: / .i f. 2. ; 1, y. ,, W .,
s v i ., < >. grr,,p% - . 3 v. . . a- _i.g 1 6 v ,) (i ,
* *-v nn.a c4 detector soit - '
mrn' on tw N wr-* "
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. _3 r. ~-m,r.c,o_ .
r .- a_ u. o_ , . GUESTION .. -> (: .00-1ho follat 'n. , u: tion -- o t M Channe. M1 ~ %' C m wn c, u .t d f y
f,.* I ). ,, h f' 4
.3. , L ;) - t, -
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i t f d i I PROCEDUREL - NORMAL, A8NORMriLr CMERGENCY AND 4 PAGE 21 om" D I O L Os m ryr - r n., p T R n >. - - i 1 QUESTION 4.01 (1.00) . i A hydrogen bubble +" o r m e d Ir +> e reactor vessel :. ; eliminated "< i i, a. increaLim ore;suricer a i 'a n oeroture above uure thermacco le
- readinsa.
I
- c. :n a eeting anygen into the r eactor coolant sycte" via the a
chenical 2nd volone c orit r a l ;ystem.
- c. w :imizing cool 2nt " low by running ell reac*or coolant, numps, increating letdown " low to 120 m2,00, cnd -c lacing the eetion bed demineralizer :. n service in oarallel atth +he 11 K .
; bed d e n ; n e r a l :. : e r .
d, ventincv the "eactor vessel huc_ p: j c. q T, -* n f8 e< . (17 ~ (. .i vAann ,. Whtch of the c ollowir,g :nd ic a+ _ ,;s reqvtre SI reir itiation , , eellapirr - tour:aut SI th;+ hn
- i
>een securedo 1 a. RCS ,rrez ore at 1950 pcig.
t.
- b. RCS succool.og ct 25 degreet r.
t
! . ressuricer l e v s: 1 at 1 7 '. .
i
- d. Al1 StOOF generato? 1mJu_; C1 157.
t l 2 C O t C C){ ~T O 'j
-- E + f) 9 J .i s n. O. '}
l J W 112h Of the f C 11:2Winj 9tC'e q'. "ej Jr ding ,Sl nt C l e 3 r a n C O '_ _ Correct? 6 e f. S
). b t, , L 5
h[ Prr ebCh C lh( ' hh b ! .l - bh ()fi U C *., Q in the order in ohien 1+ wr .ven, e i
- b. When re vrn:naa L,mten: ~ <
'" cer the elett*.c.. Switch;r; _t done ! firat.
i J
- c. Writtan o s e r- 1 s s ; e n # ram all clearanc- holders
- c. u s ' be c b t,21 r u d 09 #:re
{
, fie r f CI f' r' 7 e k9"' pore 11 1# #
0r lect " ' O rr > L :. U C . f . C ob[ 'I
,. A !l ) .d)UunC9 'b
. 7 )Cb ab1n2 i
.) I * ' U ? e CI1 . '3 Co'
! of the e ar snee it l'*r* t the o :tr ance tc ' ": e crec cod . ' - ' ilt.-1 d ! appropr:.af ly by the opet '
; tur unor - +
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- 4. ' PROCEDURES - NORMAL, A9NORMALr EMERGENCY AND PAGE 22 RADIOLOGICAL CONTROL QUESTION 4.04 (1.00)
Which of the following statements describes the correct usage of the Criticc1 Sefety Function (CSF) Status Trees while perforr ns E0t-E-0
' Reactor Trip or Sa#ety Injection"7
- a. The CSF Status Trees are CtY monitored when EOF-E-0 directs.
- b. Awareness of Ced t' 'a t h Criteria is required at all times. but the CSF Stater Trees are nonitored enly after it is determined thet EI can NOT be terminated,
- c. Monitoring of the CSF Status "rees commer:es as soon ac the immedia'e cetion stics sre corpleted,
- d. CSF Status Trees are required cc be monitored as soco as ti;e procedure is entered and n valid SI :s determined to Seve creurred.
QUESTION 4.05 '1,00)
'4 h i c h o f 6he situatlans below recuire; init:ation of Emer'encuw 3 oration?
a / e, r ailcwins e fu ~ :p- the od position indicetori .. w w TWO rods wh:.ch are NOT #vily i"serted.
- b. ;od BENE D Low
_ i r. ; t Alar it actuated.
- c. An uncontrolled RCS H e a t o .n followino a reactor trio occurs.
w 6
- d. bn uneMD1Eined decrease in *edCbOr Dower CCCuIE Wbb1e aI 4 5 70% rated cower.
l 4 8 .$ .E X [ [4'[ C C 5 94 CCNI[NCE) CN N[XI OhC5 *8K6 6) l l
. _ _ . _ = _ - . . . .. - , .. _.
UNITED STATES sk* #8G$g'o
#. A NUCLEAR REGULATORY COMMISSION 3 f, o REGION H I
* .$ 101 MARIETTA 5TREET,N.W SulTE 2900 i o
- ATLANTA, GEORGIA 30323
%...../
4 4 1 4 1 i l 8 I i, t i e i i I' i 3 I l 1 e i
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- . ~ , . _ , - - - - __ . , ..._ -- _ ,._ _ .. ~ .-. _ .-- .... _ . _ . . _ .____ . . . . . _ . . - , _ , - - -
. gn n r.ey_. w n
- n. c. rd. C "w a ' W ac. t -
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7 e.s.c .- , o. - r e.. v. n N~n
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%DICLOGIC AL C'b 70L 00ESTICN 4.06 (1.00) e_
. i g r> _ -v r c _w n , J . .No' m.. e~1.. r-2. e. r_ u '. .'., +. A' a.; n r 0 n.. 'ab aWn .,,._4 +s n
. *J,. .J mr u. G 4 .&_, . W..; . a 4ei.n_ t.a wea ,
elloWE centurrent cooldov m_ de.n ere rinction o' the RCS. Which 1.'. e t e - ment below c u r r e c t. l y describes how E 0 o -- E S - 0 . C , ' Natural Circulat:c- "acl-down with Steen '.' o i d s without %"_ H 5 " , comparec with the Oc'icos 'n ES-0.3? a, T13e p r o ;; . > r; i f e s are i d e n t ic s,
. 1 ,
6 ' ra y ;!}ru
- n n r e .i e r e. r, 6 toclr.own and d e ? " e : c 'r : c t i o n r except ES-0.4 is done - '. e 51cuer
<,+a.
.w
- v. i~ h e .oraceGra are identical in that '
allow concurrent coul.n: down End depres00: : zeticar ercept ES-0.4 tes you nonit' PZR 1_ p o, o_ l.
- ./ .
4 o_ R. . i,i_ -j M.C e , _., n_ . . -a , , .?. c n". rm* + .' n_ , , . n_ . 5 0a - ('. . 3 ,.r_ p e-- -.. , . .
.. .-~r..,y _;,.a_,n.. ;.. g z e. .
sha
. - ,-r. c.
i m r; s,.s.
, m e *v h. o r' . n. ' r:m o r.
--; - --o " c,t.ir. -
- ingr 41a E3 n.3 u e; ; OZP 90RV ss the priury method.
- d. ?mpereture 2na pt-scure ere decretted an I.pecified ir. renants or an alternat :q 2 13 in ES-0.4 eic + c o n c u r r -e n t '. s, .
QUESTIGN <^ ,07 t1.0( i T i '. > T o_. o r.,n
=t>. N Ms % 'w v, _4 n s ed2 i # o r. + %- .
#i r , t, . . - - s 4.. a a. t . w+4.
e u w e. n .s ., " r.nP rO t..- b 'D,prQOq$o
._ , m !. c_. y I.; r .' _r_ ;". p D. -n
- J r_,
- C ;_3 n fep .T.?. ' Q q / qTWC"
'e.
&_ q '-.. ._ - t.i n .1' .(
. r. ~.r,_ ?. h p rO8C,0f.I I b !) P f i r t O r 1
- 1) ODI ifI?f i ' 12 n
- c., .
t . ,,
- m . n_ r o u- ,-_ -. .- r " , c, . :..m'.
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i ,1 _ e T. r , 6 u3 r, &i.39 +
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s
- ,. _. i sk,
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m' 5**s. .* '
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GUESTION 2.0E (;.0~' W h .i. r. S rr ' ' . o_
# n '. ' o. w .; .'. .a t"'.
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. . 4.
p- p; e f'i i.. re.(
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I 4
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- 4. ;1.0CEDURE3 - NORMAL, A?NOR!M '_r EMERGENE' AND 2' A G E 24 RADIOLOGICAL C O N T R D'_.
QUESTION 4.07 (1.50) Indicate whether the fellou: :n a conditior- w:11 o!are v, o v in s C77 ~M 3 OATH , or NOT: a) Containwnt croscure of 37 a. s i ' .,. . b) All 3 S/Gs at 25% level and AFW F2ou of 000 .c . o n . c) RCS Subcoalina is 10 d e m_ nas and PZR les1 is -
*21.
GUESTIOr 4.'O ( .50) Uill adverse contairment c o n d i t ; o r. ' cause affec+e- control rocr inticatiens to :ndiccte higher or lower thcr cetual condition '; QUESTION . . 11 ( . ~5 0 ) Pil1-in-the-OlerM : In accordance with 090 12308 ' 0 :- w e r R ange NI "-1" enc-ion - +- c' a u s r.. .,.. r. . ., a m.. . a_ . o_ r. e....o...3.,m.
. ._y r.o _. ,4 4 ,. . c. -,,e.+.
s e_ . _ ... +:._..-
>+ .,,.e, n.,+,-
+ s. . _a r,
.. n_ r.
e r,v a i to 4 07. reactar mawer anc 4 1ms tb n O '. reector power :: v a + oe
- w. : 4. h. . ;. n _ _ _ _ _ = , . ,
i3 g3 c t':1 r n n .n
, .4m <. , u r, sr ?
Wh=+ w a.. *',a.- .. s. c, h os .+ o. f'
- h.i ' .V ~c o=.= . - o. : '_ - , n_ d. .- 207 v '-
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, g_ i pp_n_ ,,,...,c_. s_ c. . ,. u ,a wh'ch c #
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OUESTION 'i . 10 ( 1. 0 0 In a c c o r <ii
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}._ t t i . . 1 O I a 1
- l l
i PROCEDURES - NORMAL, ABNDRMAL- "MECGENC" AND 25
- 4. A C E
{ RADIOLOGICAL CONTROL
\
J l 4 DUESTION 4.14 (1.00) l State how the N o r e.a 1 Containment Ccoler2 are nn-tarted .a rter a safeguard s v, c t e n. i nit:ction tienel e eceived. f, (addres: GecVOnC9 Of O W i t C h S a n - r~* U l d ~- i O n S > 4, O'..ITC_T.TGN.
- -- . 4 . *. t", ( ."O' In ,ccordance with 0-OP-023 '
Emergency Oiese: Genertor r hoW is *he start i failure reiey r e s e t '>
- n. om t e e+.*..*,
4 s T. r 0 N <* .Oni m . w h = +. r ' 2 r. +-
- c a n c.'. ; 4, 4.on 4 c._ _.a>'~.e_.s
_i.ei
- h o_ v ', '. ~. _ , so r. n. =. '.'. o r
- s. -
N. . o . . . ' ' ' m, '*4n_o. 1 , d e c i .3 n c t i o n <' o r the O r' e c e t : n c. :'rocecure aliere - er.t - heet;' i , OUESTION a.1 ri.00) ea<T, , s ,, '1 a.:s+ ./ syi .sa r a r -, r n, m,+'m
- , o. g .,e r o +.- I I o. v1. w ,.g- w 4'.
A .e.> .+w j r., c..s ic C. 's .- s
- s A .s ,
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i
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W.lIOUi C o , " l e . t i n -' 2 E C =' a i o x7 e , '":.f7 0 , () 3 C O >-; 1 1 N U ~ ) ON (~ X '" .GE xr,$ t 'e
- a. : r, n r r m .nn.c.q
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n^ra. m. ap u,qr c s.c. w e..r s; N r. v.
. AND o. A r~c 'A EkU50'_[UU5U5[~UU55E0[
QUESTION 4.19 (1,00) _ist all the valves which reresit:an as a result af 2 Phase 8 (*P') i isolation sigocl. t DUESTION 4.20 (1.50) 4 l With rod control i r- autanatic wh 'e at 90% , avr f what are a '.1 tho immedicte coer etor actions . # :: 4
-r r q : e -cd d opr ( cs sow no T-w tric a
,r o> -a m>m,.. e. .s s 4
. r. O.. N n.ac . 6 n, 0- . '_ ..
'C4 1' :
a r a. ' '. ' 'srC " '. '. e .m. c. +. .o. r,
- C 1
- I
-l DUESTION a.29 (1.00) Ourina i r. n, lonenta'._n o' w ECA ^.0 ' '_ o : cf : 1 A/C c'o u c r ' . . red ,' a t F E3r b ' bhbtU b b k' l I t hC[II .9 ~hI"" bIOCUdUr *h9UId
) t'ih bPbPbtbT pe f9 r E X P 'L A 1.9 pflF.DTTO.N w . w s , l' s ' u
s - eon' v ( - -> a * ,, Yl ; , l "[ J E.h i I f J ' b_ c h e c e. 'er El te6 i nc*iar cr:ter;r relatively nerly in the ;- - o c e a u r e and
'.J L t h 1 !$ 3 r > 31, r 10 t : ' C o ni 1 * ; U r, -
- 1.3 n iti th? 70 7 . f'31 '. o '%0
'as 'er secur:ns- SI ea'< '. n t o n;I nro;- i me, cI c .] ._ I u ), +,.. .
g
*, e Ir J C C C r d ~i D C 9 ' : l '* i O
- C C' - 0 7 5
- T4IS s
$ 0 .' ' C V 11'lC DIO #[CW O.J1DS f
i # C" k 9 r3 n #, !) r 1 n '1
~
w 1I" !g1I Ol i Ci *11CO kC (.' f i 1 .' t 7 (., I' .' > 12nCG Nj* '
'9 r 52 Q ') I(~
1 e k .d e 4@ . h . ., , r ( '. -- g f .f 4 r, t e c n. v.4 - '. " low paths a'v. v :lver. l .iTF#A
. C l's T E C 0 7' V O4 [ O N T I N U O lj N t7XT ' ACE '
t '4 t s I 1 l 1 J i '1 l I I
,. .w---.-,-,%,,_-.c_,,-.m m._vw- -_--w ,mm-.. .ym- . _ _ _ _ . . , . - - , _ . - ~ . , - - - - - - - - - - - - - - - - - - - - - . .
- 4. PROCEDURES - NORMAL, A9NDRMAL, EMERCENCY AND
- AGE E7
~
U D 5 b[U U 5 C E'T E 5 s M5'T - ~ ~ ~ ~ ~ ~ ~ ~ - ~ ~ ~ - ~ ~ ~ ~ o QUESTION 4.2a ( 1 , 0 0 .1 Define 'Inside the Target Tand" In accordance with ON0?-130E,a ' Operations outside the T a r :3 e t Band'. QUESTION 4.25 ?1.00) What condition (s) would allow a Terparary or Short Tern Operstcr Turnover V9"SU5 ~ f0rD01 Shift IUrnOVGr 0 d Include - 1 a part nf four answer any tme re<:t'ictions which .a, .,pply rd documentetion uh';b sy be e .t i r : d . na n.,- e e; 1r _r 0 p, 2 .4 ,c o, ,, . ns r3 ) G. D. O,5M m ~n " , .* Q n 3 g h. wr p
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hhb b POhitorea to deternine PCS CDOLDONN- according to ES-C.2< "Neturcl CirCUlJllon r,391dayq a7 O U r_ so T. T. 0 " - 4 . .". o r, - ,A, >i. n ? 05.~, ' L 1 -: 3 or 120V 1 t e 1 I r' = t r i; . .it
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w 1/ to the u .: OreCCUtion to 'VDlo ter;ue:ns re<c 4: 00 tc le<t then -,etm <'i c o . n::u, ins 3 neactor tr1D h]5 a Ot GCit rr9d7
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! I i t a , .. ! 1 t i l ! 4. PROCEDURES - N091 AL r ABNORMAL, EMERGENCY AND DAGE '8 i RADIOLOGICAL CONTROL i i t GUESTION 4,30 (1.00) Functional Restoration Procedure FR-S,17 ' Response to Nuclear power Generation /ATWS", has the operator trip the turbine es one of the immediate actions. However, one of the najor concerns in the ATWS t r a n s i e r,t recponse evalurtion: s the excessive RCS prescure developed ds'e to significant heatu,n of the p r i n.2 r y coolant, Since keeping the tur b1ne on the line would mitigate this temperature "ise. why is the turbine tTipped 3 n / W a '/ ? I i I 6 I I i ! I t l I I
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1 l EMERGENCY CONTAINMENT INLET OUTLET ^ COOLER FAN (A, B, OR C) (2903, 2904, (2906, 2907, l OR 2908) (28 0 2812 i SWITCH POSITION ; t,;;' OR 2905) OR 2814) a w. .. l AUTO-FAN NOT RUNNING - ! (NORMAL CONDITION) : $..; _. 2 3. 1 l AUTO-FAN STARTS OPEN OPEN OPEN 1 i ) HELD IN START OPEN OPEN _ . 1
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- 1. PRINCIPLCC Or NUCLEAR POWER PLANT OPERATION. PAO: 27 THERMODYNAMICSr HEAT TRANSFER AND FLUID FLCW ANSWERS ~~ TURKEY POINT 384 -86/09/08-CASTOR C '
ANSWER 1.01 (1.00) C REFERENCE NUS, Vol 4, pp G-D Nuclear P w i- Plant Operator Trns Prgmr HTFF and Thernor Sect 2E CNTOr ' T h e r :tia l / H y d r a u l i c D rincpler and Appi;cetions, II'r pp 10-43/44 . App A* Pumps /Centrifussir Operating :s t Runout Conditions (3.1/3.1) l ANSWER 1.02 (1.00) c l REFERENCE Comprehensive Nuclear Trainin3 Operat:ons (CNTO), pp 4-16/27 001/0007 KS.13(3.7/4.0) ANSWER 1.03 (1.00) y,gWO (( p-% @ ANSWER l.04 (1.00) 1 normc1
- 2. t h i c:b l e
- 3. thimble
- 4. nornal
- 5. normal REFERENCE TPT CNTO Val II 13-27 ANSWER 1.05 (1.00)
- a. Larger
- b. Longer i ,
1 I i 1 t 1 1 i
i e l 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATION, PAGE 30
~~~~55EE5665U555C57 5E5T~TE5UEEEE~55U~EEU5DEE5E
- ANSWERS -- TURKEY PolNT 3&4 -86/09/08-CASTO, C I
REFERENCE , West. Rs physica I-4 I j ANSWER 1.06 (2.00) ,
- a. RTS s .5ea) ,
i b. Decrease
- c. Increase l
- d. Decrease
[ REFEPENCE Steam Tables i 010-000-K5.02 (2.6/3.0) ANSWE< 1.07 ( .50) False (+.5) REFERENCE NRC IE Info Notice 04-70 (a Sep 1984) i TPT Lesson Plen for Requal Cycle II-1985 , I ! 011/000; '< 4 . 0 3 ( 2 . 6 / C . 9 ) l ANSWER 1.08 (1.00) The Moderator Teaperature Coefficient (MTC) becanes negative over core life to soeb a degree to over-compensate for the effect of Doppler only. (+1.0) REFERENCE I CNTO, " Reactor Core Control *, pp 3-37/40 i 001/000; K5.4o(3.4/3.7) I h I I I I l l 4 i i
1
- 1. PRIPCIPLES OF tiUC L E A R F0WER PLANT OFERATION CAGE 31 THERMODYNAMICSr HEAT TRANSFER AND FLUID CLOW ANSWERS -- TURKEY P O I tJ T 384 -86/09/08-CASTO. C ANSWER 1.0? (2 00) a) Unit 4 (+.5) due to a lower Seta coefficient at EOL (+,5) b) Unit 4 (+.5) due tc *i T C being less negativer so Tava rivst decrease less to add + reacsivity) (+.5)
REFERENCE CNTO ' Reactor Core Control *, pp 3-21 ? 'cundamentals of Nuclear Reactor Physics"r pp 7-31 001/000; K5.qo(2.9/3.4) E K5.10(3.9/4.1) ANSWER 1.10 (1.50) Since #ree convection heat transfer rate under subcooled conditions increases es e function of the available temperature difference between wall and bulk fluid (delta T) E0.252 the heut transfer rate '. c the R> coolant in the core cree vill increase EO.25] causing a r. increase in core enit temperature E0.25] increas:n3 the available n: tural circulation driving head E0.25: which wil; cauce an increase in ncas flow EC.25:
- thereby increasing the cen ective heat trsnafer capability of the RCS.
The highet mess " low will clso cause EO.25: e corrective decrease in fuel element temperature. R' c_. c-. t" O c t4 C C_ TPT CNTO Vol II 14-26
- v. mi.e cy 0., ,
m.,..,, m ,- ANSWER 1.11 (1.00) When the valve is nearly shut the entire cressure drop is acroce the valve EO.502 A greater percentage of the p r e s s,u r e drop becomes c function of head loss ;0.502.
-g.-
When the valve is throttled the process is isenthlapic E0.5] anc when pressure reduction is due te '"ictional head losses the process is net isenthalpic E0.5]. (diff, ,2tessure due to 'h' as 'm' ine oc , as the valve opens) REFERENCE TPT CNTO Vel I 10.72 (22) camp. v1vs. 2 9/2.2
i i I t i 1. PRINCIFLES OF NUCLEAR F0WER PLANT CPERATION, PAGE 32 i T ELU557[5 i
~~~~ UERR557sERICs FREET TEE 55 FEE ~55D__________________________ _
ANSWERS -- TURMEY POINT 38a -86/09/09-CASTO, C .i 4 i ANSWER 1.12 (1.00) I Coolant tenperature. increases n it riows upward through the core CO.SJ. As a result, DNDR is lowest towards the top of the core E0.53. Lp e. n_ ~e tm c - TPT CNTO Vol II 13-34 ANSWER 1.13 (1.50)
- a. This curve :. s based upon preventing hot leg ter.perature f r o c. reaching a seturation temperature as power increases. the difference between Th E Tc
- increases.EO.252 In order to <eep Th below saturation, Tavs ust decrease wit.h powerEO 25.] l
- b. Ta maintain minimun DNBR CO.25] 2 Ensures that the avg. enthalpy et the vessel enit does not enceed the
- enthalpy of saturated 1
- quid.EO.2SJ
- c. At higher pressures, a higher Tcvs is neccesscry for 15% quality E.252 st lower pressures DNB occurs at ~15%. At hicher oressures, the ^f
'uality h 1
water may be :20% before DNE. o c c ur s . EO . 252 f
<7
/ f /[.M- ~k 9~
W 1;~20 gr..e.r.erNCE o y.g,c ! CNTO~Vol II 13-53 ANSWER 1.14 (2.50) i , 2. LOCA Loss of inventcry SL9/CLS contraction /cooldown o f' RCS
- b. RTS RTS I RTS l decrease
- c. Low Pr r pressure, stoon line pressure ur high containment pressure.
[0.25 ea,] 5. L. ('owlgy .v;th La w f a ,, ( gaa y/t .r s s , / -C N19[ f r , REFERENCE TPT CNTO 14-32 I
... - . ,.-n--,. . . . , - - - - - , - . - - - . - - - - - - - , . - - - - . - - _
i i i i e
- 1. PRINCIPLES OF NUCLEAR POWER PLANT OPERATIONr PAGE 33 ;
~
j EU5R566EUdE5C5r~EE5T'TR5U5EER~5U6'kLU56~ELUU 1 , ANSWERS -- TURKEY POINT 3&4 -86/09/08-CASTO, C ! t i ! I i ANSWER 1.15 (1.00) i ! a. decreasing the number of P20 molecules results in a longer slowing down i i length therefore neutrons travel through more fuel at epithermal energy { range decreasing the resonance escape probability. ! j b. A fewer number of H2O molecules in the core results in a higher 1 j probablity of neutrons being absorbed by fuel atoms. _; f- REFERENCE I TPT CNTO R:' Core Control 2-9 ; l-4 ANSWER 1.16 (2,00) i 4(l 3 ; ! The HTC is temperature dependent and it does not change linearly. At HFP MTC has a value of Open/ des.F at the core inlet (557) and -11 pcm/ des.F ; at the core outlet (619). Cor calculational purposes -4 pcm/deg.f for avs. moderator temperature of 508 deg. F is used. This value is snaller j than the core avg. MTC of -5.5 pen / des.F. 1 , The Moderater tenperature does not reach Tavs. at the core midplane. Since
- power peak is in the lower half of the core, Tavs is reached below the -
core. midpoint. g} g E e ; REFERENCE -;, n 'y j_a n~~ R ,wysp %v c a /, ,, )< /<j ,, i TPT CNTO Core Control 3-45 j ct ( O'i - Vb i l ANSWER 1.17 (1.00) 4 l Increasing the Cb increases the enount of spectrum hardening. Since the j absorption cross section for absorption of baron decreases at higher i neutron energies, the effective boron absorption cross section decreases E0.53 as Cb increases. Therefore the magnitude of the DSW decreases E0.5]. ! REFERENCE j TPT.CNTP Core Contrel 5-16 ! 1 I I i ; a 5 . i, s 2 i i 4 4 4 l i ! f i l l j t i
--r,, . .. _ _ _ _ _ _ _ -__ _ - _ _ _ __
- 1. oRINCIPLES OF MUCLEAR POWER PLANT OPERATION, PAGE 34 l ~~~~iUERR507sERICs sEEi TREssFEs Eso ELUi5 FE5'?
-- ------ ------------ ---- -- ~ ------.
ANSWERS -- TURMEY POINT 3&4 -86/09/08-CASTO. C I I ANSWER 1.18 (2.00) 77 /o - } ->b Eank overlap is used to provide a mot o uniform dif#erent: 3. CPW and a go3e uniforn en:a1 neutron flu > distribution dur.ns control rod ncneuverc. W d (A non-uniform a.:i 21 flim d i s '. r i b u t l e n could cause abnorr.; ally high power rneaks in the core terulting in fuel d a m a c e . r/.Q A un:forr dif#erentici worth - always ensures that "ad otion produces a change in ' e a c t i v i t y . C 7'. 9) L.c.c. c o,r.<> . y C c TPT CNTO Core Control 6-28
- O f, .O .9o 0. '
f, N Psa 'n1C
. _ R- 4 1.More % c,e.tive MTC r0.5]
2.# vel deplation at core bottom E0.5: fuel depletion is due to the il 0 L Plv: d i. s t r i b u t i o n flu p e a 'e ;t upper core at EDL E0.52 The nea2tive MTC oroduces i 'are ne,at,'e a ro:ct:vity in the top o f' the core rt EOL then et BOL. f%f d x' , / c p f / y- /D csg.JO.52
^
RErERENCE TPT CNTO Core Cont ctp-21 'j'.[p, g" 7h M b / M " AAj', j . * "^y4& q4., f (sm y.
^~ ,6 , g9' sd
/ '%4LA t . - b
?nN_ . g '%p r,
~. . a r.) o . ra-n i.
/t / f'
- a. Hich v r e'at;/e +' l u / - cruces a areater m
rocct .it"/ chance s due to CR"4 beinq-
.c r e o o r t i o n a : to flu
, tip /"l u: avs. therefore, the higher the ' eictive 010: the areater the c h a n 4'e.
. m (0.332 fur area /0.5 "or Exp.)
- b. 1erser e f'f e c t for the .:ddle due to cocorption of neutrons whic" have a Tigh probab:1.:.ty of causing #:ssic,. Wheress control rods at the edge absorp neuttons which h e: v e a h:3b probability o' l e c k. 2 3 e .
i
- c. ti has S i h e r wort? ,.a, Aen inserted t! demres:es r the "lus around itsel',
this increates the flv> n other "egioner when 12 is inserted the #1u>
- has been depressed therefore its worth in lower (then its worth in 2n
! unrodded core). cr -. o,r_ r m,.,.c y C e-North Anna PDP- pp. ,11 6.*2,6.19 Obj. : M / A 0 01 - 0 0 0 - --C . n : (t.9/3.a) . i TPT CNTO Core Con.ro! 6 '. 3
i 1
- 1. PRINCIPLES OF NUCLEAR POWER oLANT OPERATION CACE 35
~~~~55ERU55YU5EEC5I~5555~5k355EEE~5U5~EEU55~E[5U ANSWZRS -- TURKEY c'0 INT 3E4 -86/0?/08-CAST 0r C n^ [J. oC p.
.." P, 5.
71
. (1. 9_ A_ )
- a. Without RCP-driven pressurizer spray no a d e c,u a t e means of ,ixing loop-pressurizer enitt. (0.75)
- b. Provides reasonable issurance
- hat even a "airly rapid temperature drop .
will net esune moblems r with c lots of core chutdowr, m :' r c i o .- (0.75) REFERENCI Westinnhouse background for ES-0.2
- w i
5 1 4 i i i ! ' I 1 I l f I l i > - - - , _ . . ~ , , _ . . . . , _ , _ , , . . . . _ _ ___ . _ _ , _ _ . . _ , , _ _ . _ _ _ _ _ _ , . . _ _ _ , , _ _ _ . . , _ _ _ _ , , _ _ _ _ _ _ _ _ , _ _ . , , , _ . . _ _ . , _ . , , _ _ _ _ , _ _ _
l , 1 I I
- 2. F' ANT DE3IGN INCLUDING 3AFET'( ED E M E R'J E N C Y SYSTEM 3 C' A C E 36 ANSWERS - T U R '< E Y POINT 3R4 -86/09/08-CASTO, C ANSWER 2.01 (1.00) l 3
- p. e -
r r e c u. s L ._nc TPT SD9 ' r Z n' a n r' Precsvre F e l :. e f ' - - . i
- 37; TP7 DWG 5610-T 0501 T P ~' SD40 'L'.c.uid Wacte D i n o a s t, l * . C lo i v 2 n., n2, 7' / o. sn o. i A u, . n, 4- ( "u . ~ ./ ~- s e. .,
n .vu- e v e n. o.no
~
. ..n.0>
- i. n l
i RErERENCE t.pT _4 , ca n. .a ptw,e o .. ; c e. u,nm
^
m - ( ,. . n o< 3
/$
CC
% h 7' 0 -S'-bV ;
R.- c. c_ c. f_ e N.L. -r
-oT 6 c_u n P ~ ~ _ ' . . 'u t .' . 3. . .
.$ . c.
On m eu ,e n v o n_ , saa. . nm os r a,_, . o. <, m
. e.a )
ANSWER 2.04 (1.00) 3
- o. r_ c. r_ u- c o. < L- e_
i VEGP- Training T e n ., 7 Volv :e 07 p. *6b-3 and cig. 16b-1 & 6 VCE, CE S e f e g u e r d s. :ower Eycten, pp. 2 -' & 20
- r. o r na o n r1 c'.e,n_T, ab s c
w cq
.) -
n-ud ,.[ b, () n. . f' s . b O. (u ,a,0,-' - .k3 I 4
'l i
i i 1 I i l
. ,- -, . - - - . - . - . _ . - _ . - _ . _ . . - . - - - - . - - - - , . - - . - - - - - ----n .n., . _ - - - - - - - - _ . - . . . , . . - . . - - - - , , - . . - -
o . -
- 2. PLANT DESIGN INCLUDING SAFETY AND EMERGENCY SYSTEMS ' AGE 37 ANSWERS -- TURKEY POINT 3&4 -86/09/08-CASTOR C t
ANSWER 2.05 (1.00) d REFERENCE Turkey Point. Requal Lessen Plan, RCPr Fig, 16 I 003/0001 M1.12(3.0/3.3) t
- ANSWER 2,06 (1.00) l overcurrent cod control switch trips are defested E0.5 ec2 l REFERENCE TPT SD 140 ANSWER 2.07 (1.00) ;
a) Prevent reverse flow from the VCT (+.5) ! l b) Prevent lifting ti seal and having it hang up (+.5) REFERENCE ' TPT SDB 'RCPs'r pp 27-28 003/000; PWG 7(3.5/3.9) I e ANSWER 2.08 (1.00) l I Backup to AFW; Unit 4 Condensate; Demin Water Storaget FWRU Bypass (+.25ea) j c REFERENCE ' TPT Requal Cycle IV-1785, Oay 3 TRT SD112 'Condencate and Main Feedwater*r pp 6/7 l 05?/000; K1.03(3.1/3.3) l l t ) : i t l l r b E
._. _ _ _ _ _ . _ . _ - _ . _ . _ _ . _ _ _ . . . _ _ _ . =
_. . _ . . ~ . . __ __ _._ _ . _. o . - l i l ! 2. PLANT DESIGN INCLUDING SAFETY AND EMERCCNCY SYCTEMS t' ACE 33 l [ ANSWERS -- TURKEY POINT 3&4 -96/09/08-CASTOR C I ANSWER 2.09 (1.50) s
- a. 1. CCW HEX 3 (3) (0.2)
- 2. TPCW HEXs (2) (0.2)
- 3. Lube Water Systen (0.1)
- b. 1. CV-2201 (TPCW HEX Gutlet Tens . Control Valve) (0.4)
- 2. Closes (0.3) l 3. Allow all ICW to be directed to CCW HEXs (for coolire:u of
-l vital safesvard equipnent) (0.3) fi. - e rC o .r_ Ni w- re
- Turkey Point 7 Requal Lesson Plan, ICWSr pp. 4 & 10 076/000; K1.01(3.4/3.3) and EPE-026
- EM3.02(3.6/2.9)
ANSWER 2.10 (1.00)
- 1) 862 A and D (RUST to RHR) (+.25 ee for any 4)
- 2) G64 A and ? ( fi'- S T isolation)
! 3) 965 A, B and C (Accumulator Isclat;cn)
- 4) 366 A and 0 (GI Hot Le3 Injection)
,4
- 5) 063 A and B (RHR to MHSI/CS oumo. suctions) .
l REFERENCE t c, T. c-an o,-. 4 arrrc'>
-uuu r,-
oz' aur T .c r. r, ea o.1,4 . , .~, 006/000; M4.02(3.6/3.7) i j ANSWER 2.11 (1.50) i 1
- 1) RHR HXers (+.25 ea) i 2) RHR Pump seal coolers l 3) SI Pump oi: coolers and seal g l 4) _7 41c r s Q W) @ { T'4 t, j yf'
- 5) CS Punp seal coolers
- 6) Enersency Contairment Coolars 4
. ~p I C C -. p.
-_ C fj C C t
! TPT SD40 *CCW', pp o J
! 008/000; K1.02(3.3/3.4) i i
4 i 8 s
ll 1 I 1 i I l. 4 e, m. ni at ru.m e, n e r' y r smu .u, ru u,r, ums-u tinvn- r* f r-r v ,a,,mu n r_ M c e r t u r' v.
- .m cm v. C T. C M
- C is A. . (_7 C 7 0,
( ANSWERS -- TURKEY *0 INT 3&4 -06/0? '0G-C ASTO , C A f f n4 i V (c Y ! l (up q ,.o cu o. n.so . (1. . v o ,r f $ jo S f Q n i o, . nao_p . ['.
.ac t. o p +, a..n r , rn...;, y p p n1oeng r n., . e ra _, _y i, g
! b. The-RCP will not star t dee to r.t o.o n. i n ,-: of the O' P (contector o .p e n ' ihe { not 32tu will h r> e a 'O' sla.,nal i r' and a 'i' eut thus t r i c c i n -.: onen
, 1
,hn I contactor this- will result :. n a inst c: s : n a . ( I ', to the 'End' "lete '
t 4 i
,rior
) +o th- l O :sc 6.17. e r . E1.0] !
I L R.r..rrRENCr
.m. .
TPT SD -8 7 CPS j j v / A g g ;.; r_ g ..4.q . < . .Sns, .,/ t MM . > ' l l a. CT's a r ._ . sed #ct overcur"ent protection.
- W' ^ 'b f' b, Each ci . ' C er;t c r is e q u i o n' e r' with o - switch.
?., ground detection v o l t r:e t e r 2nd I l pnascJk.OWLt
.._v l c. A - ey operated two gosit:en switch an the bre ner compartment door at i the 480v load centet 'O'. Rotete the suitch .. o the 'Enersenci' por: tion, t
- r. b, ee J- eG4 ,
l 4
- i REFERENCE ,I*
l ! ] c. +l as c rs a ,' Y t e bg-L yi,% s
- / c - f " f c.
> ? . .
9 p ,z ov u or c
- n it.;w ( L,+ t i 6. (; w vvstm
! ANSWER 2.14 C. 00) j a. ?v distributing the eedwa t or L . m .sn inverted 'J' nocclec :ttached ' ' i to the dictr:Detion r :rc the rina w:11 not ensto iallow.rx- c los7 c' . 1 ! *ege. - i
'. Density at the stean t u 's t ce car i:dered -s i n c e the d e n 2 _ *. y vill sary e .
I' recording te oower level. This 15 due to the char 3e in e tec , pressure from no-load (1005 pui) to full Icad C .~' 7 0 >51). :- I^ F
.Ve! ec.1 -
Eq
. . C C.c w D. u4 . C :q=*7L.
' I w-==.-i s .
- c. i y< cs ~rW .;. ,
. . .e e. . <..w . .v LO55 Of CCW f104 WOuld inc r eC' 0 l t e ' 2 '0 e r ;. t e r e of the 'lvtd .. ' . .e all !
I EyCien [ O e U.N thOreby GeCTCCEina ihO ViECOD .ty Of thO C11. OeCT UCCI n g; viscosity .could esul+ r
~.m t o r c;o e appl . ed to *5e oeit; e t s'_#t a id t * '-
Exeed would de ar e cc e. CO. 75: a r i k I f t 7 li e
. _ - - - w - - - - . _ _ , _ - - - -
- o. co ,r u. . r.
- n
- e
_ _c r_ n, .u, T u. ri n _ r. n e.
. c a. .r r_ T. v. a. . u. n c._,u.c_ ca.~
c c u r v. ca y ev T. c .u se p es_ r;:- 4. 0 ANSWERS -- TURKEY FDINT 324 -D6/09/05-C AST'J r C RErERENCE TPT SD 13 ANSWER 2.16 ( .50) (thernally induced) natural circulation and head of water fron seal t a r, k m 0.nc cae a . ,a R*CC, _ _D.Cm ),4 P C C _ TPT SD 13 ANdWER 2.17 (1.00) The instrument power i s s o.n.o l i e d through 3 SOLA transformer. The function of the SOLA transforner is to orovide a constant voltese s e p o l '. . c REFERENCE TPT SD 4 ANSWER 2.18 (1.50)
- a. Lecd [0.5:
1
- b. EDG would start C O . ' '5 2 breder would be rocked out CO.25].
- t. Sufficient oil pressure vould not ce developec foi coact down due to I
shaft driven puno coastdown, :pect'ic311yr pocsible damage to +he . turbocher:er. - EO.52 R.e r r :.c_ y r_ c_ _r_.. . TP7 GD 137 3 ecf 3 o tt. r. , s e +a
,c ,2 n s c.s,u n-)
z ep -. C. N b V 1 I.,g . no.4 1bjeC V . m. c- sJd
- b. WOUld 1njeCI lOGG Of "udUndancy # GP stP3' 50F[ly ') . G 2 C. WOUld i n ' e c t- no elPCLt1CCl t r i t "> 1..n a C P C C b i l l t )> ~ i
(( UJ
- r. WoU r i n a 't: C t , s o s -3 i b l e PJtlure to t e C 'i n i. C 01 ' ' oVerspeed a
+T1rs a fid 10 C a l l '1'
.,;y i r_ r, .t-'_=-
s ip , t J
- e. 41 o O . li I'C I 1 I6 j '? C , [ I Su 0.75 REcERENCE Lvw
'l 'ww vc- 'w- fr,,)~ s T t' T S3 " -
'h
- lo gs%'
t 1
,c
".: Mr/
- f. p4 3. : + T q is * : i r, T -
4 : ;. ru7 d1
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- a. , (_; c 4
d e.
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. e o r.. b,u
, r r
& +
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- c. ,
I O g{' , 9 Fj'* ._.O ~}f_
- p. .
, . ,s. s + . < o c' ,
n .1 5-- ,; - ,.5 - - - _ u _
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, ., c, g..
._. . .g-
~; l - s L ,C 1
- e. a *, _ ,, ,
l m- c_ r. ,. + r : , 7- T- . cg
.c -
g mas m- 3 g
* ' , = 4 . -
A ,+ . '
,,._.,. J s,
i .g. e . :.
.4 s Ql+ . _ - .. . _, a 2
.: . s . -- .,
I I 5 :.g e t4 .. 1 I I u g' !. P'.b- t-. ,'- ,p-. s s , i , r, r c r . ._. r
, . 7 c., ..
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D.* C_ p _ J 9_ ANSWERS -- TURKEY POINT 2E4 -86/09/08-CAST 0r C ANSWER 3.01 (1.00) O REFERENCE Turkey Point. D r a w i n;3 5610 '~-L1, Sheets 9A and 99 064/000; K4.05(2.9/3.2) ANSWER 3.02 (1.00) d REFERENCE Turkey ooint, 3DCS 53- pp. 2 & 9 041/020; Kc.14(2.5/2.8) AN5WER 3.03 <1,00) u. v REFERENCE T, D T. C' a, q p p C'
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ANSWER 3.04 (1.00) .i c.; ) A r ra only (+.5 ec; b) Arm and Actuate e, c e r . c N- r, e
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TPT 9D105 "Stec O v.m p Systen'. pp 0-16 041/020; K',14(2.5/2.8), K4.19(3.3.6) ANSWER 3.05 (1.50)
- e. F a l s. e
- 5. True
- c. Falte
3, DJ S T R U M c N T R AND r n N T.i O '_ R DAGE 44 ANSWERS -- TURKEY POINT 3 F. 4 -3 6 /09 / 08-C ftST C r C REFERENCE TPT SD Rod C o n t.r o l pp. 16 # 29 ANSWER 3.06 .1.50) a) Nc n-Ur gent (+.5 e3) b) Utcent c) Urgent L.cFrc.er1rr TFT SDS ' Red Control Systt - ' . pp 06-48 001/010i M6.05(2.9/3.2) ANSWER 3.07 (1.50) a) Felte (+.5 ea) b) False c) True g r e, c_..q.r >; r e.
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ANSWER 3.09 (1,50) l 0; ,v r m>4 <</ f -'I ,'q' L
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- 3. INSTRUMENTS AND CONTROLS PACE 45 ANSWERS -- TURKEY Po nti 3 ?A -86/09/OS-CASTC, C REFERENCE Turkey Point. HD 1005-01 ANGWEP 3.10 (1.00' I
- 1. Manual E0.22
- 2. Hi-Hi Containment Pressure 'P' [0.2]
- 3. Hi steam f' low c o : r: c i d e n t CO.22 with low steac. generator pressure CO.2:
or lov Tavs CO.22 REFERENCE TPT SD ::P S p. 30 1 ANSWER 3.11 (1.00) 1 l 1. RC3 pressure 525 +-10 psi E0.3:
- 2. RHR suction from RWST (MOV-062A/P: E0.32 end R u, R Pt: autlet to RWST or alternate low head SI valve 'MOV-S63A/5' E0.3' are closed {0.12 REFERENCE
- TPT SD ECCC o.
. 18 i
1 ANSWER 3.12 (2.00) 4 a, open closed open i closed l closed
- b. F :,n starts, outlet opens, Inlet / Outlet bypass closec m e e rt _ r .r_ p-r e. v o r_
TPT SD - 40 r e. m tLs pa ._ ,.4 m n
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controller selects the 8.igher of the twe TE's for central of CV 2202. E0.52 a c_.c c_ h. r_ >Lr e TPT SD 40 I I I
4
- 3. INSTRUMENTS AND CONTROLS C' AGE 46 ANSWERS -- TURKEY POINT 38.4 -86/09/08-CASTO, C ti ANSWER 3.14 (1.00) p '5,3
- a. C would start at 78.0 ps low header pressure CO.25] after 30 sec.EO.252
- b. No [0.5J '
REFERENCE TPT SD 40 ANSWER 3.15 (2.00)
- a. Inverter is supplied from AC (30766) and DC (3001-49) CO.52 and auto tr nsfers tc clternate :0.25] MCC 'A' Lts panel ELP 317] E0.25].
- b. When control 'ods are in notion the trip setpoint of the rod deviation bistable is changed E0.53. The change prevents fclse clarms from spurious s 3nal inputs E0.5].
n c e n c n. m;r e. nrn-TPT SD 006 ANSWER 3.16 (2.50)
- a. Channel III S/G 1evel and 1st .: t a g e pressure CO.25]
-or- prostemmed S/G level 1
Feedwater flow E0.252 and S t e s.m Plow E0.25]
- b. The output from the FC is converted to cir pressure by er I/P converter E0.25]. This pneurstic signal is used by the valve positioner 7 increasin pressure to open and decreasing precsure to close E0.252.
- c. De-energize CO.5] Hi Hi steam generator level (2/3 narrow range > 5 secs SI 5 sees
?" trip and low Tavs 554 deg. F 20 secs r0. e.
e e. .; i REFERENCE
- TFT SD 11 t
- 3. INSTRUMENTS AND CONTROLS c' A C E 47 ANSWERS -- TURKEY 001NT 3&4 -86/09/03-CASTO, C ANSWER 3.17 ( :' . 5 0 )
- a. A tow speed stop prevent: the puop frca decreasing below the speed curresponding te (21 spn) E0.25] in the auto mode E0.25]. In nanual
- 0.25: the pump can be lowered to the speed 2 0, u a l to (7,5 3pm) a loue: vrlue EO.25]
b, (LT 11/ provides a signal to nodulate LCV ll5a to maintain the nor al bend). at 86% level t' 115 uill menerete - e backvo. cianc1 to trit LCV 115c tc the full holdup tank divert CO.32. Hodulation of uCV 115a and the backup trip to di"e-t will function only .I the tue positien switch is selected to the ' auto-divert' positicn.50.5]1N the VCT position fell letdown flow is p a c. s e d to the UCT E0.5: ri e .e c e p c Na r,r TPT SD 13
*t. 7 f ANSWER 2.18 ( MO )
,. no
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- b. Cherging Clow d e c r e r: c e s until actuc1 level decreases iroicting l e t d o u r, .
After leidpun toc'.M ec pressur rer level 'ncreases unt'l <* C2 5 reactor to p'" level wov]d eer,t in vei tn increece until calid and rORVs er e relieving wet c HM 7
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- ---.--------- ..----------- 1 ANSWERS -- TURKEY c'0 INT 314 -06/07/09-CASTO C a+ hiac hi r r n.on a .- r. ., . tn n3 t,
- a. Scinu:llet:en :0. C
- 5. 1. Closes 3/G l i q u :. d sa pl= isolation valves (2900 20017 2002) E0.22
- 2. Clocec S/C blowdown ECU; (627EA,0,C) EO 22
- 3. '
Close'. blowdown d 's : : p .-clve to d i s c h a r ;3 e canal (6265) E0.72 preepu e r.<re. TPT 3D H10 pp. 37 9 35 f I I l I 1 1
-- --m.-r ~ -- - , - - -- - - - - - - - - -
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- 4. PROCEDURES - N O R t1 A L , ABNORMAL, EMERGENCY A t! ? OACE 49 RADIOLOGICAL CONTRCL ANSWIRS -- T U R h' E Y c'0IN' 3 f. 4 -86/0o/03-CASTDr C 4
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ANSWERS -- T U R E Y P 0 "> T 184 - 8 6 / 0 0 .' 0 9 - C A S T O , C (d!S W E R 4.06 (1.00) 1 I4 p, E... r e.r.,. r_ e. r e-T. c. +i c o n _ c_ e_,_ n 3 ,e n. . %, 000/011; EA2.00(3.4/".o) ANSWER 4 07 (' 00) z
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A reactor has hoon operating at full power for three months when a manual reactor trip occurs. All systems are operational and the steen dumps are immediately placed in the steam prescure control noce. Ten minutes after the reactor trip, c11 RCPs ere tripped. Twenty minutes after the reactor trip, Loop 1 RCP is jogged momentarily. Which set of traces (a - d) on figure 1 174 most closely representc the previously described events? DUESTION 5.02 (1.00) For each of the following parameters compare a Core Thimble Cell to a Normc1 Core Cell and indicate which of the two has the higher vclue. (rated conditions, average values)
- 1. Totcl power production
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- 5. DNER GUESTION 5.03 (2.00)
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- 6. Pressure (0.5)
- c. Entropy (0.5)
- d. Temperature (0.5)
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Q U ES TI0 t! 5.08 (1.00) ; Refer to fi<ure 3 1354. E X P '_ A I N u ; r, the chance to the differential w ,o r e c t u r e decreases as the vc1ve it ooened. e Connarina w01cina s ae a ni a 4 s a e n t s ( I -P2) to ( t. ei u _ p i 3. s>, 00ESTION 5.07 (1.00) Pestrictions on F(0)(Ti . mi t :. n c l u d e p e n a '_ t i. e s due to uncover and reflood rates, nost-LOCA. i GIVE one o*k* b e s .t s for core hel:ht - restiictione on F(G)(T) AND explain Wher, and why it tu estrictive. GUESTION 5.10 f: .50)
% f er to f iqure v
& W- ' T a v J' vu, P rm e r ' ar# 3r suer the followino. w
- a. On the arsah w e curve *A b c; u i d s t h e. --': : m u r c.r rieratino v loan s
- ei,craturc 6
'J D 3 ]1Ven s y s t P F- P T' e r '3 u r 52 0r a , ' 2 P l j. P i f .JT P90C;Or eOWOr. E X p l C I. rt t h L' b.?SiL POP -l- r 6 D h s
*A* nt W M '1' it h;! e OC%Et.V9 C1000.
- a
- b. O f 3 p)I *3 9 t't 3 'J P O s t i ^; O h hWO d iiV O T 29 CODCitLn5 '3 r d T O *,
- I C 9 9 d e 'j . 3b310 ibPGv 'WC
., COndit: Ln1 C. T:pl3in Why c i:- e 'C' im 12 ." at ' T. ; u . . t '/ and not 15' m ' 31_ +. y l
T y 4' $ y 'g P. ,#, T C C. O_ D Y _ f 's.l [ ] [ s' *a _ .. N i_.i C- I. e n_ )J. *[ 7 V " D [. C.. I_
$ 1 Y, T A i ---e--,mm---- _ _ -- . . - , .- -. - , , , , , , _ -.- -
o .
- 5. THEORY OF mJC'._ EAR POWEP PLANT OPEFATIONr :r'_UIDS7 AND ;' AGE 5
- m. J r._ o; r.1 n. n.
e, . 4 -
- e".cos a Mtth regard to the synptors of r small bevh LOCA7 steam line breaL and feeducter line break ancuer the followin,q.
- a. E: plain uhy Pressurizer level dec: 7ases on each of +5ece transients..'.7E] ,
l b. Por e t, n a l l breek LOCA (prier to EI) ctete has the r ollowing symptons
- . n i t i a l l y ^e mond. 'incresse/decreace/renains the s a ": e ) E i. O
- 1. Tsve
- 2. Steam Flow 0
a 'a' / cs 7 -+c .,, n. .'
- 4. 9CS p r e c,s t r e
, c. State three poss.;ble inititation signalc which nay i n _ t :. s t e SI upon 4
i ; stean . .11ne
,0 : eca cecident.
Ev.,y, a .: 1 I i r.; U- r r T T rua m "s . 4.m (. .4 .go) l a, E::p l a in why decreasing -:R 920/0 ratio ' noderator/fvel. _ '+1ts in a j reCuction of the recen nee escape ptobeblity,
r. h e
- b. E:s p '. s i n why decr e as ing the <0/U retic increscea :ne value of in s1/-facter 'ormu.c.
gt _t J'r...' t s* !r T O on c. a 7 m i, u" . (i n s - E: alain two reasons why 4
'M e co-nutuu n o d e r e r, o r - o n ! ,- ouwe: d e e c t vndo' -
$ 4 est;na,et tne actuel de'ect- due to redirtrlaution ct 9: O '_ . 's non t r g 1.'00 ppm 2 c a l c u l ; +,i o n - > a _ e r- af MTC _
- 4 m .: W d ea.<. ::-T 2 . ~' b =
OUESTION 5. 4 ( 1. 0 0 '> c.n, ca+ , . ,. . . , ,+w > y - v _'
- b.s.i n o '.' ". ~~ ~.s ..<y r.=..:- ' .' sn c.: ,
'- r s . ~ g o. o, ,a e , - I .
c., a _u.-.: . - .n_ n 4 o r +.on I . 6 concentecilan. Include in our <nswer wuther OPW incre =r / d e c_ r e :" , rum.: ns the a c n. e and ahy t' does ze (sts., #.: A T E G D P ' 05 CONTINUED ON NE)7 PACr A*vrai l
i . I
.s . r.. um e n q. ysior msj rmtmc+ .
_ ru: - e nv.. g r e,s e iuu+ > T, n v:: c_ o sn: s r -T D. ye r c %i i m_ , a r - s4 on :, s mr c - 3 THERMODYNAMICG
^
r.> uwa o c c T. . T O M. = "s e .' "w ( ' .t) ^, ) . EXPLAIN the two so m foi control rod bari overlep. r T, T g N D [ "e > a . .< uc e / m. . o p. -
%. e. a. c. +o s +'
..., m.., o. g ags .7 7 s i s c.
. +.3c 6. w t, c,._-,*..". -s <a h i uC.
_, ' 'r51 t, r,1 a.
. O. m .m Power Dictribution ,1 EOL and esult ir . "eletively #1st powt d i s t r i b u t, i a n ,
r;lJ-e c T. I. (o n1M e r. a 1. 's / o. . 9. () i, car c d. r a c r + r> t, r o a, .i g y .rI -g _ L, *w a- u,' t. u '+: .4 4. ~a. 7.
. - s - 2 i I
+
., 4 v .. . L A ". 2T1s N rd's .i "t1 c. -^ -o ce o i.' . sJ : *=>.'.'4.'*.,
w in the greclect react:.vity change due to centrol ad incertion. Note: Assume 100% powerr E a n .' . at 220 stepar 9 0 '_ ,
- c. An v ec cf high relctive flu; se. l a '., relctive Clu ,
- b. Edge of the core va. niddle of the care,
- c. Rod il (Inserted) vs. rod 72 i nserted besidt rod ti.
F.) {s! C 0et! T. 6 nM E w . *1.p;
/ 1 iA e 'J ~&-s '.,
j 1n P O '3 p C i t '3 e O [. b --' O e 2 NOtVF2. 3 i r C V ) . *,1 G I' CCOIdOWn* it l' CiIi'Pb9d i i .' ' ' h2 RCS be boreted te Cold 5"v.dcun concent';*. ion prior tt REE coc:.tcur,, inis 3 e t.a inn e n ,= i.i .' t , .i .ri
. an n / o r. - h. n,. " ,
- 4. o>* r -. ** aCT~Vr ( e v. o & ' n o ,t
. cn o.r the ysten, concidet ing t'._, answer he 'o: lou;n3 que:t orn
- t u s. .,. m . .. , ,o
*.,...; . . - . . , n. ,
,y..,.,_.,n. . , , s . , m. 4. n.a, . , u .., e. ., e.
. e - .i r.. +
'<'n. I ' ~ r. ". .' '. . o n . O i. 7Mi
~
r, g- rs - .t- s-- f, - . 2 I C.-- + ( 7 f.1
. 'Q f ; *,.-
. c. ( f, T. +
.c m m { t. 9 C-.**i < : ? *> >
*# mp9 c
p*
-- - /a n. ; v.i Ln c 3 g vs -----.v s *7 ,e
- - I.- )-
C +0
- r.). l.,t-u F C 'I T.4 L ,ly. .J . .+n&) a -
Chat 3r9 the tua > : ') n s r .; p 33;r+4 ng t' . OI t oij e frer zo'd ImJ p g e 4 n. n : ,. 'l. ~. tw4. m- r. +u p. .F] O - 4 1 o ., r r e. 4 "r r i.l 1 m c < m
'.f.* t , S,r n. , '
. p. i r_4 1y r
- S._ ,2 q C * ' " c, ? f ?, O "i- - 5_ I_'- I (a ~
(gS h[ . U.g _- I
'. e .i ma k-).
T-m tt7 Pa b.1 -" y l. ' ' T F,,.!T , --r y a y ; l 1 1 h 4 I t I. F h
l l
- e. T.u..r_gav, m n. N. U C '_n c ' ,- r' 0 W. _ ? P t_ c.t N.
. . . 'i- n_ : c_.? p4 T. 1 n_.s ,
. c. !_ u_ m_. _ r .u. . n.
. : m^s_
rc 7 THERMCDYNAMICS OUESTION 5.20 (2.00) . A rod drops and stick.s at the care : i d - ,n o s i t o r from full ,ausr concitiens W l tll 011 rod 5 OUt. A R 01210 r- Irlp dOO: DCt 02 cur. If ti 12 C O n c i t i C P' W t.-t r e to pers1-5t for Jn 9'st9nd9d CGrlOd Of I L :L e ( w tz l 1 .efanc T's 11n'.ts). What Will be the effect on the Encore Asic2 0 f s e t o f' the " o v e r' :ange NI for the quadrant in which ', h e dro,npe0/ tuck aod occurs. Includa a discussion of '
'er:On e i f. 9 C *s s OnC O d R 'p "ItiOr C # O 1 C . D"'- 50 1.
QUESTION 5.21 'l 00) l TS 3.2.: regtires p e t. 2 -' ce reducec 'a "S. 1 +' a r ina113nac contro; rod CannOt bo :12 CDOd o W 1 L l-~ " O h00F . t ls tht bOS~ : f C T- "9dVCinq m 0,0 tJ O r in thi5 .i I t i .t -J t 1 C D9 i k i i I s
< n ,, _ .o -
o, m a y Os,m,
f *
, p p, t
~
- i
/.
- s. f a? y T.. O Y P_. T C. M C.a P.
s 7C muT F M, , l. ' .] }]> 'I' Q s... Q! , +-10 - T N. Q v D. t . l_J M. _ . Ci.' Jri T .* T "1 n A. ;' 5_,
- a. . .
- c. , - . ..,.,.
i 'P f 0 F tO f ' 'j U " e s 4402.1 c od 40'. c 2 Flou 2 3ths OUring " ,i.e u o M a rj e c s , unteh c, n n. C ". '. h n. C. . c "* og' w',., h e. . (.a.- n i, _ r_ n '. r. e + .- 'y e m. t .' i n n_.
- t . +w.h o_ fi '+ - m n -' t+., n D .' ' ' t< -o ., "in_ d o_ " ".
operatiorP ri tt r-s u c i U '!Tnr
+
Cr + -- r, 5 (. 1.
- A s <p. )
. C C s N O. CN1b+ bbbs bb T' C)II9(t1y . b b C I E b d #$ th6 HP 5f3'Um lineU.3 when H O ', LEG RECIRCULATION lt Itcr hedi (resume both traine of RPR 2re s
e i . /
,00's s
s.: # -[ O 'ps. ,'l aE31n3 4"9 ' .I 3 C C, ,C 'iU D, sL1 .\.'-
,ie g FeCi0CU.. "1CO : C i ' ! - ' V O ,, 'I' .
b Q g .:.- e s .n p: s.t
$ e
. e. gic ,= 4 1 -, c t.i r.,r.; c.7i b< g t 1. g m.; ,
p p..mr s p r. i.i . w, +c ,. r.
. i. 7rjr - [hp > - . ( 1 +wb o._ r.
(, f 3 L li ' US9 ' n i ort $ i7 UO C Q l d'[ lOJ P O C 1 P C U 10 !, [ r) D , C. 'Oth-iTm 1 "i s E U ." > y ; Ot' 50. 4 ind CDld 109 T wO C l f- C .12.ifit 3Tt90U L.'1'. fd . ORO t P o '. I l & s' ' t ? f) YO' dot 1 ?tv P t? C l I ' 3'i . b ;O O I. h 0 f' D I 3 '. n l .'U+., s O I . f .
. ' . , O f.' l. 3 f/ , tO C4U pUBp i
i T.,1. . t.,. A \
- a. e <> s Q }a 3C '_tT .s* f} >s t
/ 1 , A A. ,
.s . ()'
. - '3 s &
y 4p, ri v . .
+' *hp M g ."I r , 4 ; ~e - %. y:
r _; &_ -- ; + g , e' ,_.T j-} + a s.*.gq[ p ) p e.%. I.i. r. ,] i *n
.t - t .i -* -". ,s^ 7 i
.E g . n _ bs E
s
.f*"'
b Cb b h I 1. , bb b h[,b[ g I ~
-. . bE C '
b 9
.MW E.) fiC' 1 d D"s h * * <f 9 4 , },. .') s.} . ', M J . t g'6.- v % u ; 4I ] i
..s s , s . } ["t ' ' * '
i s. - V. J P. % O_ s+ .-
- i O. {#
1 1
*. t .' -n. , 'tm s' - ..I. t I. n f., r.t (i '1 +? i f. t.1,~ 'I P i a i r -
. . r. i. _ p y i. ' . I. '. L' t, ' - _ .. .'l . .
- rid L . 21 J '. I 'J D sa1' S j
- h. . . . o; h .
- f. 1. q w. _. _3., .sc o.,_,
3., . n r_< , . . 4 c'ti . 1
+
,a"~ .' ~.+ P r ~. rir
. - " c '. i .t '.' n. .
. i pE Wi1) i 111 2; r , - 11y _ O;c '
( } , t,; pg. 'y 1 9 f._f y , 9_y{ r ~ - r'; e _ : 1Ji Dn 4 s > 1 ' '9 . c, 's 33,3 p. . .ng . 's ,3 '. , ; r, r ,. o r, a
+ t i ., P. r.,
A i .,, q- n, . s . - s , _ .
.5 ,L.
. m
=
. . 2 m ) p b. -
- e. ' b Nm
. . u _ - -._;
I (
- n. .
p-* v _
< gy ..
b f pp -- . 1 s a . (f ' {f (.{*
- y. 4
_ - 6.g T.a P, . e +
..sq r,5 i r p*me e e.a ".g p. . T.
a A'+ b m.:
. e 4 , .s a. -.. i f' I si w.s '. p1 gi.
. wn s' ) . "
-"1 F,..f"'.( -
}
a 4"'
%.".h. .( }, u} "A'f..i.
=
[' , f.f & e{,,*
. - '.I.
. .]"."'T u
Ti 7 g.,f.. f
,-,I sg3 . . 4 ge
.4.-,-- . .
,s .. 2 3 .g
+ -
. .a A~ ,. c. . 1 7. .,. r_ .. m , , +i
- g . q 'S_ _ .* f i rj '. ' n, + , 9 p r.
c3 1 u I F D 1 c': t1E" , -i lVG,
/ .* :t .t. 't 't C (, T E C '" C Y O, CCNI1NUED 0f HEVT - ACE ttt*4 I
i
- - , - .,--r -*e,--.,- . - - - - . - -. . , . - , - - - - - . - - . - . - , , - - , -v., ,,.,-v..- --,- ,-, ---- - - -v,--- ,. - , < , - . - -- - - - - - - - - - - - - - - - - - - .
I
- 6. PLANT SYSTEMS DESIGNr CONTROLr AND INSTRUMENTATI0t! C' AGE o 01JESTION 6.04 (1.00)
Of the following signals that de-energize the diesel '%3dy To Start' light, which is also inttriocked to .o' event the d:esel fran 'stertin@ w
- a. Low Startin, Air nsure ,
De U E' y 3MitCh i n Iyp35i Ce ,CW w mi - D /.1 d -* d n ,g L e'/ e i d+ LOW DrelUbe Oil P r e s.c u r e
- e. Lou Prelvbe Oil Temperature Q (.I C J>. CTTON .A . () R_ (1A .AQ) u One Of tl19 f O l O W i fl j C G P d i t i + )2 .
Will P O 3 ); l" in 2 t ?Octur trip? ae LOW flCW On 2/2 delectGrr 10 /' l O O p ", W I)e r. E-7 O r:0 2-[.
, 3
,O 6 OM f. 3 O W O fi
. J/.- '
C e , e C , 3 I' C 1 Il ,/.-,
- O O T1 . D W[}i' #~d+
- c. Low l o w a r, 1/3 detectarr in 2/2 : cops when C'
~' and t' - 0 .
- d. aw +' l o w en 1'n eletector' in 2 .' ' loops when P-3.
Q.---
! ' .r r, T. T. n .y /
.s . O. I. (4. . A.. n '
IndiCC+e WhP'h9f ' hl [ O 1 1 '] W i n ] :1bVCL1Cn9 W O U l -j "0020 DD8 .:. t e .3 '*- C U " 6' 5 '4,
- 2$
4 k ^YI vw in
- h. h. . M. . .k i- 9 [4. b, ,' ,
. t, h w , l. s' t t s. Y. ~ ~ri* M. $.! - h'b t 7. [.C. G. ,
- 3) P I ~ lI d 7 (1St i k !3 '3e . 7 ii i ' C 9 .O r d ', 3 0 ' O 0r 10[ #
P t .F N 4 r, l n , u
) '21. _0N, M. o d e Control i r- i nvo 'odce w 7*e Tsva bI- 6 d e 'a c, w
b) [ f) f Ir k O 8' Y I [ .-9 dQdO C f ) Q * O 1 [ I- " O ([ F) f * * ,[% 1Ckp
. ' ) O,.,
_ C C ,'. - O -' ./ * .,1 ( f[p _ , f_3 m"M.. h_ l ; 'T, '; _g"r k.*, 9 v. I I a C (5 e_ p'4
- b- *
. r_ I_.
L . C I. D. . . +.. p
- U. ., ! ;7 ,p "3 -~c'
'r *"
. ^.-*O c_ * '. '. G_".'
r 1 't 1 K V I ^ ' }~ C [ ;' ' '[ Qj P ]?,I T [ k;(j n ]?j f. { )( ~ ^ % C [' 1 yt#?' t I i l
e
~. _., rri., t,r - ,- .,,n .v 1 1.c.
n <w v. . . n , . n, De
- r n.) y4 -sc iyF v.} J : ss .i. u . *UFf
. 8 h#U .4O
' . , u . u ,? r1 'i *,,J'
,1 .
______._______.__r,-cy1______.___'1;-_ _ _ _ _ _ _ _ _ _ _ _' c\ J ! . 1 T_ _ _ _ _ _ . _ _ _
*a , e >n,s.
!. ruuus ir c r. v.+n-. 9 A.o'I r Answer TRUE or CALSE to the followin:. w [
- a. With no rod 7.ot 00 i n :ecqress .
and the red; in
- ".3 nucle t te "od s.oeed 4 neter o r, the control bord indicates s tmeed of 0 tv. s s I b. The bank o v e r l a .o Unis wl' O W., Y cauc* ste,au :. f the red control ban?
- selectar su:teb it in AUTO cr MNUAL.
- c. C ri '. ", one o '. 4 h. e + h r s_m..
. i. ~m. o _ ,_ '. o. r '<?.'.t.' w r",, n_.,e .'..f+. r_ 0. 4 .- _ n_. +. + h o. P R. D d.
*5 g 7 g-a u p ,, . , o. d- n*.
- q,i,> gn . ( .+ 7 2.,
4 QUESTION 6,03 (l.50) Indicate whether t h .: following -,111 cw: 2 2 Rod Control C y s *, e n '.l 0 0 E N T or 1 M n D.M. -tip .ia r._ u, T ritt i_t - r p. r.:. w u r. ... l 3, ), ! p..i e. *
._ r. [
- s . ' 4.
- A. * } .! f h. '.l 9 f, hp . nB.
1 q
.. t.
s p. l 1 N. , ,1a2 p_ f t_ '.] 1 e p+, M 1 _ l b) Slave Cycler fcilt to c t. o r t count:rm voon neceiot of s s
'Co* m.
( ltes C) L O C S t.' Circuit CCrd li' the ?OWer Cabinet. q.t_rt.aT'Or..
, 1 o' e AC e s ('ui ^^) e . .
,b a .s ) I[ It b Orb 4 .'- .i C r 1 *e ( 10 fi'S 1 rr COlVCn i W '_ t ; t., h 2 2 3o ree r O C r ' U f. O l O _11 C n
, f h t. 1IC (8 '2 [ ? I#',P "Od t J i t fi'.I T . W .,2 1 !-- L9 L* l. O CL '. O rd 2n ".s O 1 'J 7 r' D, i C O ' '. ' " ' 5 1 1 i O !T: 5 n ? .' bJ
- 8.' sed COro ~_i ' l 3 T q"'. ' )
n, ro !J,, L. c we F
^re www.i m. 1' r e
f _ _ . - ~ _ . - - . - - . .
?'.
i a) - OUD " E. s. O fi Q '! h) i - F ~f' "
* * )' ." . . O.O ',- 'T . .e'".
* ,f P-4 , b#
b) C ',' ' f !, U n D 0 t C t. O I sf Ot I 3
*U~ stO" t
- 3. 1'"
j 4 4 4 ,_ ."r ']'1 c) Into udi;4 .. R aiy . y r. , 4 q l I
.j lf 5 n ' f j 1w f,
b
.,. () I ,,
Q[ # l l I a 1 1, 1 1 k '.h I T 1 l )q f I f F) el T Y. Y[Y1 4 I 1
)
I 1 d L 1 ( l I a i I I
---fy=.---a p- we.iy .=*e.gygwy.ty'it e w " wee- WW y--.-e nw.y'nww'- -
- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INST 9:UMENTATION OACE 11 00ESTION 6.10 (1.50) r or each set of plant conditions listed 'selow STATE all functions (of 1,2 and/or 3) which would be sencrating a rod movement L;gnal and STATE the response of Bank. D rods (ini outr no movement) to this ci3n21.
Sunk D at 200 s t e p s. ,
- 1. Bank Selector Sw. 2. IN-CUI-HOLD lever 3. Plant Condition
- a. Manual IN Urgent Failure
- b. 'D' HOLD Tre# fcils high
- c. AUTC HOLD T ava-Tref +4 deg.F QUESTION 6.11 (1.00)
List 4 sets of ECCS related /alves "equired to mit. gate a LOCA which have their control power breckert racked ont deeing criticel operations. QUEGTION 6.12 (1.00) List ALL of the 91gnals that will cause Main Steam Line isolation. Set-pointe not required. QUESTION 6.13 (1.30)
- 3. Refer to figures %397.1 ind 4397.:. Reactor Coolant o vmps. List all interlocks which must be met tc Ltcrt an Oil Lift Pump (OLP'. CO.5:
l l I b, RC? 3A start neonence i 1. in crocress i w r :. . e . DLP control sutr t to neutral and OLP bresket closed) u:th 400 psis oil pressurt. Pr ic r to the enpiration of +he 120 See timer the signal from *and' gate 1 'sils o,e e n (no signal 'O'). Enpis .- tho resultent cffcet on the co uletim of the RCP stari sequence. T. i . " QUESTION 6.14 (1.00) While operating a charging pump :n ' % rnsel' a ; t g o :. f i c a n t reduction in CC flow to the fluid drive hec -: changer occuen. Assuming the rumr ir operating between the high and low cpaed s t o p ': EXPLAIN how ths : peed of the Charging PU%7 Will r e s p or;d , (TtflY CATCCCRY ') 6 CONTINUED ON .i E) ' ' AGE ***<>i I
1 as am,. 4 _a _ --- J.
- 6. 'L. ANT SYSTEMS OF9ICN, CCN'70' r AND I N S T'? U M E N T '.T I C N NC: l
.aa s.-
m .,* .,..,', .
- 1. .3. [
90 #QP (C f 1 ]')" O } d: 9 3 N 1,3 .J W @ T C f ; ~ ,O '; '/ , CP! jq C 3 O f 2 ( l'g] ff p ; i ]O * ; f0p(Of 1 to 3P07 nas been transferrerd ^_e INV AS r o o TW 3 /. . D v:c- '
- th tr nr.c f'e r
, INV A9 C+;tpU+ V O }, 4; a ( ( _ W3S grt*3ter p F h ,3 t of INV ]A, EXF' alm ' I' y t Tl 3 . h i d. g e *. v e '. +v tm ,e. w oi.i.' e h. i ' +. r. - ' r e _"r_. m_i h o_ n g '. . '- s '4.-. o m. . . iv h c. r
.s u i.> <, tisc . w. . g .
N1 i r , t P V 't. O h * , - <U tJ O f . 1 fw J . . % . < . s f,. . .. .a } l J .. T' m 4' i C_]sfa
]8.
.m .- e ,,
._.s ,p1-- 4 4.. ;.g -,.- s. ' I .?
, !.,.- . i -e , r, p p , 3 +=
.. _ 3 r. -
i e.-:3. ,. .e r, ms , .4 .; r, ., .;,
.c r '...i ' ":ir e.j a c rT o0 's. ^*
1
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- 7. oROCE9URES - NORMAL, ASNORMAL, EMERCENCY AND PACE 16 RADIOLOGICAL CONTROL DUESTICH ~'.04 (1.00)
Which of the f o l l o w i reg s t a t e m e r, t ; desen tbes the correct usage of the Critical Sc r ety Function (CST) Status Trees while per f ormin-; E0b-E-C
' Reactor Trip or Safety Injecttan3
- e. The CSF Etatus Trees cre ONLY ta o n : t o r e d when EOP-E-0 directs.
- b. Awareness of Red ' _:th Criteria te required at a '. . +1nes, but the ,
CSF Status Trees are nonitored cnly after it is dotern.ined that SI can NOT be terminated.
- c. Monitoring cf the CSF S ta r- - Trees c o ra ta e n c e s aa con as the mmediate action c. t e r L cre completo( ,
- d. CSF Stato: Treo; are required to be tonitored a toon as the procedure ic entered and e vclid EI is determined to S vo occurred.
QUESTION 7.05 (1.00) Which of the situation: below require; in:.t ation of E m e t g en c y C o r a t :. a n ~'
- a. Followinc. e ro T r i .n , the rod . easition indicatort show TWO rods which are NOT felly inserted,
- b. Rod Oc nk D Low Lin:t A l c r n, is actucted,
- c. An uncontrolled '~: C p, u eatop a l l o w :. n o a reactor tr:e accurs,
- d. An unm:pl ai ned decr eate :n reactor po - tr occurs w";1e ct 70X rated powe .
I f*V+*# CATECORY 07 CONTIYUfD ON NEXT ' ACE ****.*) t l t --w-- - . , . nn,..-..,_..-_,_.,..-n._,..., , , , , , , , . _ _ , _ , _ _ _ _ _ , , _ , , , , _ , . , . _ , , . , . - _ , _ _ _ , _ _ , _ _ ___ , _ _ ,,
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1
- 7. 000CEDURES - NDPML, ADNOP"AL, EMERGINCY AND PAGE 17
! RADICLCGICAL CONTROL I - - - - - - - - - - - - -. - - - -.- - - 1 1 .i OUEST10N 7.06 / * .00) i Which of the following - e: icons c orr ectl "/ d e r: c r i b e c the basis #ct allowing 3 RCP recta"t. in E0P-rR-C.1 'Res,oen;e to Incdequcte Core Coc1:ng'. ! 3. "elps to m :. : the SI flow to ?"otect r e a <: t o r vessel from cold a water.
- b. Once subcooling 11 ctablishedr e s t a r t :. n 3 the RCP2 ,cips to l collcpse voldt tha' .: c y have formed ir the reactor , :'c z e l head.
c, A:. lows restoratior, of PZR ,'r e ssor s control ' sing nornal s p r 'a y s
- d. Wovidet for coolirm of the e core when seconderv d e n t e n s . e" 12 : t i o r.
daec r: o t alleviate : nadec.uate core coo:in1 - i i OUESTION 7.07 (1.00) l E0P-ES-0.3, ' Natural Circul,t;on Cooldown with Stean .cid with R ') L M S
- r allows concurrent cooldown and depressuri2ction of the RCE Which s t a t e --
nent below correctly describes how EON TS-0.4.
- Natural Ci colation Cool-down with Eteem Voicz withov. R '.' L M E ' - conperes with the cc 1uns ir EE-0,39
- a. The p r o c e 'j U ' ' ' , ;fe identic l in thJt _5OY SllCW Concurrent COOldOWn i' n d Il e. k f 'J C I U T 10 0 t 1 G n , er c c o. t Es-o.a :s eene :t . slaue:
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- 7. FROCEDURES - NORMAL, ASNORMAL. EMI 0ENCY AND PAGE 18
--- RE5iEE55fCEE 55ETE5E-~~~~~~~---~~~~~~~~~~~~~
QUESTION 7.09 (1.50) Indicate whether the followin, c o wr.d i t i o n s u111 olace "cu s / in a C3C RED PATH or NOT: a) Containnent pressure of 37 .o s i3 b) All 3 S/Gt at 25% level cnd ArW Flow of 300 spn. c) RCS S u b c o o l i n;3 is 10 degrees and PZR level is 12%. QUESTION '.09 ( .50: Will adverse conta:nment conditions cause a f e c t e d control roon indications to indicate higher or louer than actuel conditionc? QUESTION 7.10 ( .504 i Fill-in-the-51anks: In accordance with ONDP 1230G '='ower Range NI Malfunction'. the Power Rznge meters. avercse reading mest be u thin . at greater ths i r-equal to 9 0 ~. reactor power and at less than 9 07. r e a c +,o r pouer nust be within _____%, 00ESTION 7.11 i.00) What are the c h u t o r *' h 3 t a d orn urn listec in E00-E-0 +' o r Wo" ;1e H451 i and LHSI pumps below which EI ' low needs to be verified' QUESTION I.12 (1.00) In accordance wi'h GNDP 1500.; 'Ste- G e n e r i '. o r Tube Lealace'-
- 1:ct the two C o n d i t i o n 's W!iich c o n s t, i t, u t e 4 initiatiun c r i t e r 1 E; w h e r- ,ee:;Ur:rer level l Snd fi r e s s u r ra c a p ri c + be % 3 t p +. 3 i n e d ,
(<**** CATFCORY n' COP'7I4UED ON NEXT ' ACE us**). i i 4 i I i
r P 1 i i
- 7 PROCEDURES - NORMAL, ABNORMAL, EMERCENCY AND PAGE 19
~~~1E5I5E5ciEEE C5sTE0E--------~
i 1 I J OUESTION 7.12 '1.00) State how the Nornal Contairment Coolers are re-started after a safeguard c o> s t e r. in:tiation sianal is received. d j (address sequence of :,w i t c h nanipulations) i QUESTION 7 . l e. ( .50) In accordance with 0-OP-023 Ewrgency Diesel Genertor'. 5o' is the start 1' f ellvi e relay resetc' n- -y. c e,'T I n. N. 7 ..a *c
< 1. . n. o )
What plant :andition is ar;uned in w valve /br ea' er " Normal" ,o;1 tion > des :nttion for *be Operating Procedure rilanment theets? 7 OUESTI.0H 7.16 (_.00) S u b e r i. t i c a l i t y a n >: Core Cooling a r <. the tua '; ; g h e s t prior:Ly CSC Ctatu. Trees to monitor durinq 2:cident _ conditions. L;:t the r en n n: n- _ 4 CE7 1 Status Trees in DECREASING orcer of or or :v. s s 1 i i J i QUESTION 7.17 (1.00i List the a co,ditions that e ' be met in order to -erfor~ a tartup followin' -a Reactor Trip v;1hout c o n.c l .e t i n a -. ECC. . i i t DUESTION 7.1H i
.00) i How '
1 the RCS coole a usina. ' 3r c : " low, if c u r . .q refuel; m aeerations - - : I with the refuelinq cavi+, . fo ., 00TH RHR .mm .o : Cell te c .o e r r t e J I n_witr e: w sxtTgp ?. ,x <. rs..e.n3._ w i I O s i d O '2 rP90.tPOd 00tif1Cationst W .' iL JPL the i mfl.e d i 3 0 e epOrator ? C t i 3 - l' i you are on chift :n the control root and the refueling su,wrv t- :n the COntdinM0nt "Oport$ they drCpped 3 'i p O n t #Uel e l e t t.' n t in Zon'uinnent' d I (virt* Citvro i a _ m.. ^s. 7, C 0 ". T. I ts " " 0"
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- 7. PROCEDURES - NORMALr ADNORMAL, EMERGENCY AND DACE 20
~~~~E50EEEUU5CEE~CU5iRUE~~~~~~~~~~~~~~~~~~~~~~~~
GUESTION 7.20 (1.00) List all the valves which reposition as a -esult of a c' h a c e B C ' c' ' ) isoletion s1Gncl. QUESTIDU 7.21 <1.50) With red control in Jutomatic @e l l e at 30% power
- What are a!! +he immediate operator acticn; if a single red dress (assume no r trip) au stated in ONOP 1600,1, " Fi* ; l Length RCC Malfunction'?
QUESTI0t' '.22 (1.00) During icplementation or ECA-0.0 ' Loss of all *JC Power', a red path C 3 i' on contcinment occurs. Which procedure should the operator per etr:' r_7 p . :u sr A> . QUESTION ? 23 (1.00) FRP o.1 ' Response to Imninent assurized Thernal Shock', ias tm operator 7 check reactive y urly icr n t e r m i n e *., l o n cr..erl. .t n , ,o u pet edure anu with lets restrictive condition; that, in the EP'. Give TWO bases for securing SI early inte th:s procedure. QUESTION 7.24 (l.00) In accordance with 3-OP-075 'AFW s y s t .' m ' , cutline the " low path; "or AFW Trsin 1 d'it ing Duc . Unit operation te m one compliance w.t' the requ:re-ments of T ec' Spec 3.U. Include in your i ;cuusion s u c *. t o discharger stean Eup; ly flow peths e r.t s alvet. ( n * < :s CATEGORY 07 TON'iINUED 04 NEXT PACE *****)
a , . , 7. PROCE00?EE - NORMAL 7 A0 NORMAL, EME.005CY AND PACE 21
--~~EE5ioE55icEE 55siRU[~~~~~~~~~~~~~~~~~~~~~~~~
i i
! QUESTION 7.25 (1.00)
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- 0. ADMINISTRATIVE oROCEDURESr CONDITIONSr AND LIMITATIONS PAGE 23 DUESTION 0.04 (1.00)
O/G 'A' is inoperabier LPSIP 30 it also inoperative. The Tech Specs for SI systems and Electrieel systens cre attached. Which ctatement below is most correct concerning Mode 3 operations?
- c. Mode 3 mutt be maintained.
- b. Restore D/G to operable status within 7 days or notify the NRC.
- c. Apply LCO 3.0.1.
- d. Startup activitics r.cy continueiMode 2 may be entered.
QUESTION 3.05 ' i1.00) While perforning fue' z h '; f f l i ; :.n accordance with 00-16002.5, ' Refueling Core Shuffle"r a change to tM prceedure is necesury md time doer not allow ncem al processing of a c,ange. The change should be ade in accordance with which o rn of the following procedures?
- 3. AP 0109.3 OTSC l' . O r' - 16 0 0 2. 5 Refueling Core Shoffle
- c. O C'- 16 0 0 2 . 7 Cefuelinj o"e a>>fflu
- d. AP-0107.6 Tenporary F ' a c e d u r e t, OUESTION 0.06 . 00)
Which rf the followin; stetrento correctly describes piapor status of contcinment buildins pene'-onc du ing re+eeling oper ct: en;T o t.n ,-.1d air , tot
- a. coor; can ce u as long au so i n u,i v i u,v a ,t tw ctationed to shut enc of the doors if conditions r e c;u i r c this acttun.
- b. P'fri t r a t 1 0 n - >23dinj #rch the conl51"tient 3 t *P o 0 p h e r e to the outside o t rn o c p h e r _ een be OPEN as long as rn OPERACLE autor.ct:c 1 G 01 :3 tion V31Ve .' in plaCd.
- c. The equipment doc' .5 ODEN but ccpable of being immedi?tely shut.
- d. The COntlinGOnt OurgO 3'/Gsen L; SECUTFO ?! d u 1Golation Valves SHUT.
( v t .* s r CATECOPY OP CDNTDHJE3 GN NEXT oAGE **'***)
_ . . _ _ . . . - _ _ _ . . _ . _ - _ _ _ . . . _ - . ._- __-____m>. _ _ _ _ _ . _ _ _ _ - .
- .
- I t
t ! 8. ADMINISTPATIVE PROCEDURES, CONDITIONSr AND LIMITATIONS PAGE 24 QUESTION 8,07- (1.00) l According to Tech Specs, the s e c a r.d a r y activity limit is _____ micro-curies i per gren and it based on e ______. j a. 1.0, Load Rejection 1 L. 1.0, S/G Tube Rupture i c. .677 S/G Tebe Pupture l d. .67, Load Reject;on 4 1 a DUESTION 3.0G (1.50) l r } or EACH condition listed below state whether or not a TSA would be '
- needed to complete the work in accordance with ADM-503, 'TSAt".
- 2. Testing of plant systems requiring disconnection of hydraulic lines which is not specifically controlled by a Tect Precedure.
- b. A tank drair, (to a floor drain) needs to be bypaz;ed by a temporary .
4 connection to sllow for repair work. l
- c. Electrical connections to elec tr onic equipmer.t placed under a surveillance procedure.
J QUESTION 9.09 (1.00) Given the following alignments <'eternine the operability of the CMS channel i uhile in Cold Shutdoun. If Ineperative indicate why, i GMS Primary Aligned OMS o ackup Aligned 1 ' OMS Pri. Aligned' light on 1. ' OMS B/U cligned" light on
- 2. MOV .*-535 open 2 POV-*-536 o p e r- :
, 3. PCV-*-456 twitch in 'clote' 3. PCV-*-455C Lwitch in 'cuto' [
- 4. N2 charged to 2090 psia 4 N2 charged to 3000 pu 3 l
- 5. Setpoint position celected for 1956 5. Low precs. telected for 45$C
! OUESTION 0.10 ( .50) 1 TRUE/ FALSE * { A Tenporary Information Tag in NOT cons.dered to be a ri Oper:ter Aid, far administrctiv- control, ' I (VA*** C A T E C O ? ': 09 CONTINUED ON NEXT OACE r****; ' I I l i i l i ' l
)
i
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8, ADMINISTRATIVE PROCEDURES, CONDITION 5r AND LIMITATIDNS' OAGE 25 l
.JbE P
GUESTION 8.11 (1,50) A ,s :i Match the description of responsibility for administration hf the tagging / ~ " eleer ence pr ogr ant in Colunn A with the appropriate indivicual in Column B. i
.c j COLUMN A COLUMN % ,
____ ___ __- -,__ ~ a) Denotes if Independent Verification is 1) RCO -
~ !
required. 2) PS-N !
- 3) Maintencnce SPVSR !
b) Nornclly sign: the Cleetance Release p c r t' 4) NUE [' of the Equipnent Clearance Order form. 5) Maintenance Harker c) Enterc/Deletec entries for Tech Spec related equipa.ent in the Equipment j Dut of Service book. I r I
- 4 a
OUEGTION G.12 (1.00) t t Pefer to c i 1> r e i S47, 'TSA Administrative O raccsc Flow Char 6's In accordance with 0-ADM-503 uhat person (by pocition) would complete the ! review required in the bloc 2 n ark ed 'A'? d P 6 00ESTION 8.13 (1.00) . i I Cill-to-the-3'an' ,
'A .consiuta or injectin-J a cimulated stanal w into t. n e channel to ;
verify that it is operablev includinc clarm and/or trip : n:t:cting retion.' [
- 3. Channe! Check i
- b. Channel Tunctional Tect .a
- c. Channel Calibration I
- d. Chennel logic Function -
( OUESTION G.id '
.50) :
a ril1- r the PLANM for the follcWing: l [ In accordance with 10 CFR 55 'f a licensee hac not been act;v11/ ; rform- t ino J the function of an Doeriint er Senia: Onceatar t i for c ter101 r af J months, or longea he shall, prior to r e s u a.i n g 2 c t ; 'v :. t i e s l i c e n c asi pursuant ta this part, denonstrate to the C o m a, i tsion thet 5; e' .uledge I and untferstanding of facility operattans and "dninistrait{t are ; satisfactory.* ' f . .
' t
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1- f f . ; c G. ADMINISTRATIVE C'ROCEDURES, CCHDITIONS7 AND LIMITATIONS -AGE 26 ( ?' 9.r W j . ' l I QUESTION G.lS (1,00)
- 7 l Provide the m i n i m ir i. r u m b e r of indiv:. duals required by tech spect for +he a
following pocitiorn to oper at e both units a t. full power. f
')
/
______ c'lant GuU'rvisor-NuclearfDS-N) I.; b) ---__- SRD(s).(NOT including the 21cn* m e r v i s c, r ( c '> ) . 1 !, c) '_ _ _ _ M O'( s ) 1 r ) d ) ~, ______,AM;) e) 3TA(if i \ 4 QUESTION S.16 '1,00) List 6. h e two individuals who way authorize equipment clearances. I i OUESTION C.17 1.00) In accordanco with A/ 0103.4, 'Inplant Equipment Clearance Orders' for clearancet an MOVs used at :n isolction boundery, toss will be placed
- at two locations. STATE the e *wo locctions for the valve.
, QUESTION C.10 (1.00) !- What are the m anic u c- :11ouable *W C q u .:; r t e r l y dow Lic'ts (ncn-mergency), ' c o 'ti p l e t e d N C r ar i 0 and less than the PAD for the for an e rip l a y e e with ; follou.ing:
- 1. Whole li o d y '
- 2. Gkin of uly : l e body ,
l , r t
?
I ,- 1 - p i L t ! IWTT%T C A T E C f) I'l' OS C f1:) T I N U E 0 O tl rJ EX T O A C, E ****T) L i . i t 4 < s - o
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4-
- 8. ADMINISTRATIVL: PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 27 t
QUESTION 9 19 \ (1.00) 3 1 Durins Unit ? startup with the reactAr about 2% power'- you find that the DDRV block vtIVe ji.s stuck rp e n and incapablefor clor3 1Q. Which of the followins isia'c'arrect action per TS? ( s ee a t t acher' tLCO s ) i
- a. Continued operation is, hllowed provided the PORV is operabie add power renoved form the block valve.
- b. Within 1 hour ensure the PORV is operable and continue power operations,
- c. Continue power operctions since one other PORV :s operable.'
- d. Be in a condition with Mef# 0.99 within the n e::t 6 hours and in Cold Shutdown within the followins 30 hours.
1 7 QUESTION 8.20 (1.50) List three r e sp otis ib il i ti e s that the Emersency Cocedinator CANNOT delesate. QUESTION 0.21 ( .50) l In adcordance with Ao 0103.2r' Responsibilities of Operators...", POW OFTEN ! should alarn cards be verified in p l a c e ') l I (Including verifying cards pulled under authorizatter by PS-N) GUESTION B.22 , (1.50) List the MIC W.% requirenents for each of the necessary clactrical systems listed below in order to conduct a reactor rtartup cn UNIT 3, assumins Unit 4 :s shutdown. , a) Unit 3 and 4 4160 MV Duces b) Unit 3 480 '
. A C Load Center 3 1 c) Dattery Chargers GUESTION G.23 (1.50) i List the '3 DNS-related ::C S p a r a n e + 2 r s as stated Ic Inch Specsr 2nd their setpoints. (Assune normcl power operations) i
( (***** CATEGORY ') B CONTINUED ON NEXT PAGE **n*) i i l P 4 l = i 6 6 f
i i i I i i I a r 1 i j G. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 28 , J-h 4 OUESTION 9.24 (1.00) ] i
- Unit 3 is operating in Mode 6 with the following conditions present
- I
. Wster level above the. top of the reccLar vessel flange 23 feet. l l O/C A is inoperative. i l RHR Train 9 (the inservice loop) is found to be inoperative due +"
i design flow inadequacies. [ ! Specifically which LCO/ ACTION statement (s) would be entered 2nd carried l out? t .{ (LCOs attachec) 4 ! ! QUESTION E.25 (1.00) I During Mode 1 operations of Unit 3 it is found that 2 of 3 channels for
- Pressuriner Pressure High Reactor Trip are inoperative due tc a gene it
- Tea t e r i a l deficiency (repair time 14 days). Using TS LCOs attached,
- determine what actions must be taken as e result of this failure. Stste l- specific LCD/ ACTION Steps that apply.
I' QUESTION 0.26 (1.50) Tech Specs defines Shutdown Margin (SDM), as used in the Power Distribution [ Li nii t s t 'as the amount by which the reactor core would be subcriticcl l at Hot Shutdown Conditions (540 deg. F) if all control rods were tripped, l assuming ... '. STATE the assunptions made for the plcnt conditicnu that [ k complete the definition of SDM, ! i QUESTION 8.27 (1.50) ', Technical Specification 3.4 alleus all reactor colant pumps and residus! ! heat removal pumps to be de-energized while in hot shutdown. ; a) What is the tine frame that this condit:en may exist? (0,5) l b) What two provisions noct be net during the per iod these pu gs ar e de-energized' 'l.0)
- GUESTION 0.25 (1.00) !
t Why are the action statements for T/S 3.1.4(Re3ctor Coolant Activity) 'cre . [ restrictive when RCS temperature is sreater than 500 de3reet c' { l (ann END OF CATEGOR' 08 n*n) ( xx*vurun *
- END 0 EXAMINATION * * * *
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560 O 20 40 60 80 800 120 POWER (PERCENT) FND-HT-100: Tgyg VS. POWER FOR SEVERAL LIMITING CONDITIONS (REV.1) , 5;ya<<d ~5 5 7 1 13-54 f l 0394C
VALVE U Pg
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- 2 3 DI ST ANCE -->
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l E l ! FIGURE FND-FF-93: GRAPHIC ANALYSIS OF A PRESSURE DROP ACROSS i
' A VALVE AND PIPING SYSTEM (REV. 1) ,
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! EMERGENCY CONTAINMENT COOLER FAN i NI e EMERGENCY CONTAINMENT N OUTLET B PASS COOLER FAN (A, B, OR C) (290dy 904, (2906, 2907, (2810 2812 SWITCH POSITION la F,p OR 2905) OR 2908) OR 2814) l m._ AUTO-FAN NOT RUNNING ... (NORMAL CONDITION) $ h,_ , 7 , AUTO-FAN STARTS OPEN OPEN OPEN HELD IN START OPEN OPEN _
. 'l, STOP CLOSED CLOSED S~. . - -
'3.4 :: C:::FERED SATETY FEATt*RES 3;nlicabilitv: Applies to the operating status of the Engineered Safety Features.
Objective: To define those limiting :enditions fot operation that are necessary: (1) to racove decay heat from the core in emergency or normal shutdown situations, (2) to re-move heat from containeent in nor=al operating and emergency situations, and (3) to remove airborne iodine from the containment sencsphere in the event of a Maximum Hypothetical Accident. Sc ec if Ic a t:.::: 1. SAFETY INJECTION ASD ?ISTIA*. MEAT RI.'-: OVAL SYSTC45
- a. The reactor shall not be made critical, except for .
low power physics tests, unlass the following . conditions are met: 1. The refueling ister tank. : .n : shall contain not less chan 320,000 gal. c ir,vich a boron con-centration of at 1 22 ,50 pps.
- 2. The boron inja:tice tank shall contain not less than 900 gal. of a 20,000 to 12,500 ppm boron solution. The selution in the tank, and in isolated portiens of the inlet and' outlet
' piping, shall be =sistained at a temperature of at least 145F. T"Jo channels of heat tracing shall be operable for the flow path.* '
- 3. Each accumulat:r shall be pressuri=ed to at least 600 psig and esneain 875-891 f t of water with a beren c:ncantration of at Icsst 1950 ppm, and shall not be isolated.
4 FOUR safety in'ection pumps shall be enerable.
? ~C See reference (11) on Psge 53.4-2
- 3.4-1 Amendments 78 & 72
_ _ ,m_ _ - _._ _ - _-_ , . _ _ , _ _ _ _ . . _ -_.__ , --
3.6 CRIMICAL AND VOLUME COSTRCL SYSTZM
- Agelicabilitv:
Applies to the operational status of the Chemical a=4 Volume Control System. - Chiactive: To define those conditions of the Chemical and Volume Control System necessary to ensure safe reactor opera d a. Snecification: a. When fuel is in the reactor there shall be at least one ., l flow path to the, core for baron injection.
- b. A reactor shall =ot be =ade critical unless the fon=ving Chemical and Volu=e Control Syscam conditions are met:
~
- 1. T"4 associated charging pumps shall be operable.
- 2. T b'oric acid tra=sfer pumps shall be ' operable.
3. The boric acid canks in servica shall contai= a t:tal
'of at least 3,080 gallons of a 20;000_ to 22,500 m bacon solutie at a temperature' ~3$ast .
1'.5 T . l . t
.~..
System pip 1=g, interlocks and valves shall be operable ~ to the exte=t of establish 1=g one flow path fro = da boric acid ca=ks, and one flow path from the refueling water storage ank, to the Reactor Coolant Systa=. )s -
- 5. TWO eh====1= of heat tracing shall be operahla far de flow path f =n he horic acid tanks. >
- 6. Th's pr1=ary va:ar st rage ca=k centa'iss not less thas '
30,000 gallons of vatar. *
- c. The second react:r shall soc be =ade critical unless ae .
following condi.1=us are met: s 3.5-1 ,.* end:itent Nos . 72 1 57
-w-, w ,-, ,--- - - - - - - - , - . , , - - - - - - - - . - ,
3.8 STEA4 AND POWER CONVER33ON SYSTEMS 1 Apolicability: Applies to the operating status of the steam and power conversion systems. Objective: To define conditions of the steam-relieving capacity and auxiliary feedwater system. I Specification: 1. When the reactor coolant of a nuclear unit is heated above 3500F, the ! following conditions must be met:
- a. TWELVE (12) of its steam generator safety valves shall be operable (except for testing).
- b. Its condensate storage tank shall contain a minimum of 185,000 gallons of wate .
- c. Its main steam stop valves shall be ooerable and capable of closing in 5 seconds or less.
- d. System ' piping, interlocks and valves directly associated v.- : the related compone . s in TS 3.3.1 a, b, c shall be operable.
- 2. The iodine-131 activity on the secondary side of a steam ge.w-ator shall not exceed 0.67 uCi/gm.
- 3. With the reactor coolant system above 3500F, if any of above specifications cannot be met within 48 hows, the reactor shall be shutdown and the reactor coolant temperature reduced below 3500F.
Specification 3.0.1 applies.
- 4. The following nurnber of independent steam generator arr11ary feedwater trains and their associated flow paths (steam and water) shall be operable whe- the reactor coolant is heated above 3500F:
3.3-1 Amendment Nos.I and
- a. Single Nuclear Unit Operation Two independent auxiliary feedwater trains capable of being powered from an operable steam supply,
- b. Dual Nuclear Unit Operation Two independent auxiliary feedwater trains and a third pump capable of being powered from, and supplying water to either train.
- c. If in accordance with TS 4.10.1, testing is required during start-up of either unit, TS 3.8.4.a. or b., as applicable, shall apply for an auxiliary feedwater pump, numps, or associated flow oaths (steam and water) found to be inoperable. i
- 5. During power operation, if any of the conditions of 3.3.4 cannot be met, the reactor shall be shutdown and the reactor coolant temperature reduced below 3300F, unless one of the following conditions can be met:
- a. For single unit operation with one of the two required independent auxiliary feedwater trains inoperable, restore the inoperable train to operable status within 72 hours or the reactor shall be shutdown and the reactx coolant temperature reduced below 3500F within the next 12 hows.
- gp b. For dual mit operation, one auxiliary feedwater pump and its
.P L. associated piping, valves, and interlocks may be inoperable i '@ provided two indeperident auxiliary feedwater trains remain operable for time period not to exceed 72 hours. If the inoperable pump cannot be made operable within 72 hours, one reactor shall be shutdown and its reactor coolant temperature reduced below 3500F within the next 12 hours.
- c. For dual unit operation, with one independent auxiliary feedwater train inoperable in one reactor, the affected reactor shall be 1
SHUTDOWN and its reactor coolant temperature reduced below l 3500F within 72 hours. TS 3.8.5.a applies for the single unit still l In operation. ! d. For dual unit operation, with one independent auxiliary feedwater i train inoperable in both units, one reactor shall be SHUTDOWN l and its reactor coolant te nperature reduced below 3500F within 12 hours. TS 3.8.5.a applies for the single unit stillin operation. l 110 104 3.s.? Q%.2m mo
' 3. 4 ::c:::F. IRED SATETY FEATURES Arnlicabili:v: Applies to the opersting sta:us of the Engineered Safety Features.
Objective: Tc define those limiting :enditions for operation that are necessary: (1) to racove decay heat from the core in emergency or normal shutdown situations, (2) to re-move heat from containcent ia normal operating and emergency situations, and (3) to remo re airborne iodine from the containment at csphere in the event of a Maximum Hypothetical Accident. Seccificati::: 1. SAFETY INJECTION /S3 ?25:0"A* HEAT RD:0 VAL SYSTDIS
- a. The reactor shall not be made critical, except for low power physics tests, unless the following conditions are ret:
4
- 1. The refueling tater tank shall contain not less
- .b:n
_than 320,000 gal. Of water with a boron con-t ' , t-t "eintration of at '. ca s t 1950 ;ps.
- 2. The boron inje:tice tank shall contain not less than 900 gal. sf a 20,000 to 12,500 ppm boron solution. The selution in the tank, and in isolated portions of the inlet an'd outlet piping, shall be raistained at a camperature of at least 145F. T*JO channels of heat tracing shall be operable for the flow path.* c
- 3. Each accumulat: shall be pressuri=ed to at least 600 psig and contain 875-S91 f t of water with a beren c:ncancescion of at icost 1950 ppm, and shall not be isolated.
4 FOUR safety infection pumps shall be operable. c t
"* SGe reference (11) on Page 53.4-2 .
3 -l . Amendments 78 & 72
- 3. TWO residual heat removal pumps shall be operable.
- 6. TWO residual heat exchangers shall be operable.
7 All valves, interlocks and piping associated with the above components and required for post accident operation, shall be operable except valves that are positioned and locked. Valves 862-A and 5; 863-A and B; 864- A and B; 865- A, B, and C; and 866-A and B shall have power removed from their motor l operators by locking open the circuit breakers at the Motor Control Centers. The air supply to valve 758 shall 5e shut off to the valve operator.
- b. During power operation, the requirements of 3.4.la may be modified to allow one of the following components to be inoperable (including associated valves and piping) at any one time except for the cases stated in 3.4.1.3.2. If the system is not restored to meet the requirements of 3.4.la within the time period specified, the reactor shall be placed in the hot shutdown condition. If the requirements of 3.a.;a are not satisfied within an additional 48 hours, the reactor s all be placed in the cold shutdown condition. Specification 3.':.; applies to 1.4.1.b.
- 1. ONE accumulator may be out of se vice for a period of up to 4 hours.
~ -"
- 2. ONE of FOUR safety injection pu .ps may be out of service for 30 days. A second safety injec. ion pump may be out of service, provided ' ' pump is restored to operable status ,
within 24 hours.- ~Di the FCUR safety injection pumps ii 3 shall be tested trate moe-ability before initiating ' maintenance of the inoperable
- ou :s.
- 3. ONE channel of heat tracing on :ne flow path may be out of service for 24 hours.*
l 4 ONE residual heat removal pu .o may be out of service. provided the pump is restored to operable status within 24 hours, in addition the other residua: heat removal pump shat!
, be tested to demonstrate ope-astlity prior to initiating maintenance of the inoperable pumo.
- See reference (11) on page B.3.4-2 1.4-2 A.T.endment Nos.101 and 95
l I S. ONF. residual heat exchanger may be out of service for a i period of 24 hours. , '
- 6. )
Any valve in the system may be inope-able provided repairs are completed within 24 hours. P-ior to initiating ] maintenance, all valves that provide the duplicate function shall be tested to demonstrate operability. l 7 To permit temporary operation of t'w valve, e.g., for survei!!ance of valve operability, for the purpose of valve maintenance, etc., the valves specified m 1.4.1.a.7 may be ! unlocked and may have supplied air or electric power restored for a period not to exceed 24 hours.
- c. During power. operation three Reactor Cociant Loops shall be in operation.
- 1. With less than three Reactor Coolant Locos in operation, the reactor must be its hot shutdown within one mur.
- d. In hot shutdown at least two Reactor Coc. ant Loops shall be operable and at least one Reactor Coolaat Loop shall be in operation.'
~
~
1. With less than two Reactor Coolant Loo:s operable, restore the required Coolant Loops to operable sta us within 72 hours _, or reduce Tayg to less than or equal to 353 F within the next 12 hours. ~
, h1 $_
- r 1:,,
i
- 2. With no Reactor Coolant Loop in ^idspend all ooerations involving a reduction in boron :oncentration of the Reactor Coolant System and immediaten .nitiate corrective action to return the required Coolant Looo t: operation.
- e. With average coolant temocrature less than 350 F, at least two j
i Coolant Loops shall be operable or immediate corrective action must be taken to return two Coolant Loops t: operable as soon as l possible. One of these Coolant Loops shall be 3 operation.'
- 1. With no Coolant Loop in operation, suspend all operations involving a reduction in boron concentrat:en of the Reactor Coolant System and immediately initiate corrective action to return the required Coolant Loop to opera on.
All reactor coolant pumps and residual heat removal pumps may be oe-energized for up to I hour provided 1) no operations are permitted that would cause di.=on of the reactor coolant system boron concentration, and 2) core outlet tempe-ature .s maintained as last 10 F below saturation temoe-ature. G
3.7 2. ouring powar ::eration or renarting'from hot f/e c h i<'" L shutdown th2 f:llowing components may be inoperable:
- a. ONE star.-up transfor.mer may be out of service provided both diesel generators are operacle. The NRC shall be notified *
, l within 24 hours and be advised of plans to l restors the transforr.ar to service. l l
l i e i
- b. Power operation may continue if- Orit diesel generator is out of service ;rovided (') ,
the rentining diesel generat:r is tested I daily and its associated er.gineered safety features are operable, and (2) either
- start-up transformer is operable. If the diesel outage is to be seven (7) days or acre the NRC shall be notified. !
- c. ONE battery may be out of service for a period of twenty four hours.
- d. Specification 3.0.1 applies to 3.7.2. 1
-aa
- l G
l
. s 3.0 LIMITING CONDITIONS FOR OPERATION - APPLICABILITY 3.0.1 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within I hour action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in:
a) At least MOT STANDBY within the next 6 hours,' b) At least HOT SHUTDOWN within the following 6 hours, and* c) At least COLD SHUTDOWN within the subsequent 24 hours. Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limitig Condition for Operation. Exceptions to these requirements are stated in the individual specifications. This specification is not applicable in MODE 5 or 6. 3.0.2 Non-compliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of t5e specified time intervals, completion of the ACTION requirements is not required. 3.0.3 Compliance with the Limiting Conditions for Operation contained in the succeeding specifications is required during the OPERATIONAL MODES or T hl'.other conditions specified therein; except that upon failure to meet the i bimiting Conditions for Operation, the associated ACTION requirements shall W met. 'i 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the conditions for the Limiting Cor.dition for Operation are met without reliance on provisions contained in the ACTION requirements. This ! provision shall not prevent passage through or to OPERATIONAL MODES as requi--d to comply with ACTION requirements. Exceptions to these , requirements are stated in the individual specifications. l 3.0.5 For purposes of determining if a component is operable for LCO considerations, the , component need not be considered inoperable due to inoperability of its normal or emergency power supply if all of its redundant components are operable with their normal or emergency power supplies operable.
' NOTE: Until full conversion to STS, when a LCO actim statement requires a unit to be placed in HOT SHUTDOWN within 6 hours. refer to Table 1.1 and place the unit on the required status to meet the HOT STANDBY MODE.
l l 1.0-1 Amendment Nos.114 and 108
,_ edu,.No, . P_edu,e r.e: . .
P.,e ..
,~ 's i , 24 0.ADM.503 Control and bse of Temporary System Alterations 1 14/ I .$i k.
ENCLOSURE 3 (Page 1 of 2) TSA ADMINISTRATIVE PROCESS FLOW CHART I. INITIATION / PERFORMANCE REQUESTOR Procedure Section 5 2 lf iTA OR TECH DEPT ENG. P'Ocedure Section 5 3 1I Inservice Equipment or Systems. Equipment Out of ServiceCearances, OR Component Substitutions
- AND No Component Substitution (5341) g (5342) l f TECH DEPT SUPV 4 procedure Section 5 4 1 I
- POWER PLANT '541 $ 4,3 ENGINEERING
/ 54.2 l PNSC l *b8-1 I 5.7.1.3 ; ; i TECH . DE PT. 5UPV Procedure Steo 5 4 3
+
REQUESTOR Procedure Steo 5 4 3 1 P O , f- ~^ProcedureNeon SY k + , SHIFT TECHNICIAN Procedure Section 5 61
+
REQUESTOR Procedure section 5 6 2
+
SHIFT TECH NICI AN 2 5723 Procedure Section 5 6 4 if
\
5.6.4.4 > PNSC c u t' f b m.m.n,.
- c. Pressurizer Safetv Valves ,
- 1. ONE valve shall be operable whenever the head is on the reactor vessel except during hydrostatic test.
- 2. THREE valves shall be operable when the reactor coolant
. average temperature is above 3500F or the reactor is critical.
- d. Pressurizer The pressurizer s5all be operable with a steam bubble, and with at least 125 KT of oressurizer heaters capable of being suoo: led by emergency oower, when the reactor coolant is heated above 3500F.
- e. Relief Valves
- 1. A power one ated relief valve (PORV) and its associated block valve shat! be operable when the reactor coolant is 5eated above 3500F.
Z
- 2. If the average coolant temperature is greater than 35~:F and the conditio .s of 3.1.1.e.1 cannot be met because one :- nore PORV(s) is inoperable, within I hour either resto e the PORV(s) to coerable status or close the associated block valve (s) and remove power from the block valve (s); otrwise, be in a condition with Keff < 0.99 within the next 6 hors and in COLD SHL'TDOWN within the following 30 hours.
- 3. If the average coolant temperature is greater than 3500F and the conditio s of 3.1.1.e.1 cannot be met because one x more block valve's' is inoperable, within I hour either res:xe the block valve (s to operable status or close the block valve's) and i
remove oower from the block valve (s); otherwise, 5e in a condition wh Keff < 0.99 within the next 6 hours and 1. COLD i SHUTDOWN within the following 30 hours. 3.1-la Amendment Nos. P: and IC2
= _ _ _. -
3.10.7 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION 3.10.7.1 HIGH WATER LEVEL At least one residual heat removal (RHR) loop shall be OPERABLE and in operation.' APPLICABILffY: MODE 6, when the water level above the top of the reactor vessel flange is greater than or equal to 23 feet. ACTION: With no RHR loop OPERABLE and in operation, suspend all operations involving an increase in the reactor decay heat load or a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to OPERABLE and operating status as soon as possible. ' Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosohere within 4 hours.
'The RHR loop may be removed from operation for up to I hour per 3-hour period during the performance of CORE ALTERATIONS in the vicinity of the reactor vessel hot legs. '
3.10.7.2 LOW WATER LEVEL Two independent residual heat re noval (RHR) loops shall be OPERABLE, and at least one RHR loop shall be in operation.
,., APPLICABILITY: MODE 6, when the water level top of the reactor vessel flange is less than 23 feet.
ACTION: a) With less than the required RHR loops OPERABLE, immediately initiate corrective action to return the required l RHR loops to OPERABLE status, or to establish greater than l or e~2al to 23 feet of water above the reactor vessel flange, as soon as possible. i b) With no RHR looo in operation, suspend all ' operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required RHR loop to operation. Close all containment penetrations providing direct access from the containment atmosphere to the outside atmosphere within 4 hours. 3.10.8 BORON CONCENTRATION The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be suf5cient to ensure that the more restrictive of the following reactivity conditions is met; either: ' 3.10-3 ! Amendment Nos.111, and 1Dg_
l 3,3 D45TRUMENTATION ADDllCability: Applies to reactor Safety and features and Accident monitoring l
- Instrumentation systems. J Objective: To delineate the conditions of the instrumentation and safety circuits '
necessary to ensure reactor safety. Specification: 1. Tables 3.5-1 through 3.5-5 state the minimum Instrumentation operation conditions. ' Specification 3.0.1 applies to Tables 3.5-1 through 3.5-3. 4 i
'.Ji.
!3 . * . ,, .<
*d >
I I i j i 7 I h ti Amendment Nos. and 3.5-1
**~- .oo. , , ,
k TABLE 3.5-1 INSTRUMENT' OPERATI3G CONDITIONS POR REACTOR TRIP 1 2.' 3 MIN. MIN. DICREE OPERATOR AC !ON OPERABLE Oy IF CCEITICNS Of
- 30. TUNCTIONAL UNIT CHANNELS RIpUN. (XH,D S 1 01 2 -
DANCY CA550T BE !!E'
- 1. Manual 1 o unincain hot shutdova
- 2. Nuclear Flux Power Range
- 3 2' Mais.ain hot shutiews
- 3. Overtemperature AT 2 1 Mai=tais hot shurdown
- 4. Overpower AT 2 1 Maintain hnt shutdown
- 5. Low Pressurizar Pressure ** 2 1 Mai= ais bot shutievn
- 6. Ei Pressurizar Pressure 2 1 Maistain % _
shutdown .c
~,'
- 7. ' Pressurizer-Hi Water Level . 2 1 Ma1=tais het shutdown
- 8. law Flow one Loop > 45% 1.F. ** 2/ loop 1/ loop Mais:ain het tabordown Iow Flow Two Loops > 10% R.P.** 2/ loop 1/ loop Fai=.ain he-
. shotdown 9A. Undervoltage 4 KY Bus 1/ bus 1 Maintain h=c
- abstdown t
~ -
i . , I l
- Below 10% R.P. operation is perritted with idw trip setting only
** Refer to 2.3 - Reactor Trip Interlocks ,
I l Li e
s , 4 W; ~%
?, 1, ? Vt
. s s-h -
3
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+
V
<c 5. THEORY OF NUCLEAR POWER PLANT DPERATION, a,UIDSr AND PAGE 29 e .
THERMODYNAMICS ANSWERS -- TURKEY POINT 384 -96/09/08-CAST 07 ,C
.s ANSREP 5.01 (1.00) , j g',4 C (. /Ly b b' .'
i,,
' e I. ,. AN7WER 5.02 (1.00) ,,
M 1. nc(sal / ,- . <
'/
*2. trtil.ble ,
e
'r' L t!'imble "
i
- 4. n o r te a l 5 nrmul -
m, w: . . a.,wr;. c g s. c. TPT CMT0 fol II 13-27 I '
- ANSWER ,
5.02 (2.00)
.c a, R ~l y,, ( 0 , 5 e s. )
- b. D c'c ( 2 3 : e y
~.
c, . IncFacse a, Decrease REFEREPUE
, Steam Tables 010-00035.02 (2 6/3.0)
ANSWER 5.03 (1.50) l_ a) decresse (no answer) (6.25 er r e s p o n t.e ) ( b) (no ans); increase W c) decrease. decrease d'> doc erse; decrease RFIERENCE CNTOl'7hermal/ Hydraulic Principles II'- pp 12-39-05 039/000; .2.05(3.3/3.6) ' o l j',/
+
l l l f (
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^ /
....____..___.__._____._____---_.___________m_._-- - - - . - _ . _ - - - - __ - - _ .
i [ f ? , l' \ l i ,4 l 1
- 5. THEORY OF NUCLE AR POWER DLMJT OPERATION, FLUIOS, AND PAGE 30 l g;.------------------------------------
} C,
'l ANSWERS -- TUF;KIY POINT 3&4 -86/09/08-CASTO, C 1. I s
~
l l } ANSWER 5.05 ( .50) 6 i l t False (+.5) , ! s ! 3 REFERENCE f NRC IE Info Notice 84-70 (4 SeP 1984) TPT Lesson Plan for Requel Cycle II-1985 , p ! 011/000; K4,03(2 6/2.9) ,, i
> l i
ANSWER 5.06 ( .50) f* It' reduces vessel fluence (+.5) REFERENCE E TPT Requal Cycle I 1 085 lesson plan ' Core Life Changes * ! i , ANSWER 5.07 ' (1,50) : Since free convection h' eat transfer rate under subcooled conditions L [ increases et e function of the available teeperature difference between > w:11 and bulk fluid-(delta T) CO.253 the heat transfer rate to the Ry [ coolant in the core aret'will increase E0.25] causins an increare it core exit tenperature E0.252 increasins the available natural c i r cul a t ior. , drivins head E0.252 which will cause an increase in mass d' i o w E0.253 j thereby increasing the convective heat tranafer capability of the RCS, , The higher'nassiflow wi Ceo cause E0.25. a corrective decrease in fuel , element temperature. 4 i REFERENCE ! TPT CNTO Vol II 14-26 : K/A El: 1.01 3.7/4.' !
' I i
I p Y t i I e 1 I t t i t t i N k i
~.. - ____ - - , _ _ .
/ 5. THEORY OF NUCLEA9 POWER PLANT OPERATIONr FLUIDSr AND PACC 31 ANSWERS -- TURMEY POINT 3&4 -86/09/08-CASTOR C ANSWER 5.08 (1.00)
- When the valve is nearly shut the entire pressure drop is across the valve E0.503. A greeter percentage of the pressure drop becomes e function of head loss E0.503.
-or-When the valve is throttled the process is isenthlapic E0.5] 3*id when p r e s t.o r e reduction is due to #rictional head losses the process is not isenthalpic E0.52. (diff. pressure due to 'h' as inereases as the vai /e opens) l REFERENCE
- TPT CNTO Vol I 10.72 (22) camp, olvo. 2.9/3.2 ANSWER 5.09 (1.00)
Coolant temperature increases as it flows upwar2 through the core .0.52. i As a tervlt, DNBR is lowest towards t' e top of the core E0.52 I j ' REFERENCE TFT CNTO Vol II 13-34 i it ANSWER 5.10 (1.50)
- a. This curve is bazed upon preventing het leg +enparature fron reaching a saturstien tempercture et power :. r. c r e a s e s , the difference pesween Th E Tc increases.EO.25] In order to keep Th below so uration, Iwg cost decrease I with powerE0.25.J
- b. To maintain minime* DNBR E0.25]
Ensures that the evs, enthclpy at te versel e::: t does not e :: c e e d the enthalpy of a sursted liqv;d.E0.252
- c. At higher pressures. E- hight Tavs is neccessary for 155 , i r,1 1 t y E.252 at lower pressures DNP occurs at 5%. At higher pr scores, the q u a l :. t y of veter may be > 2 0 5. be#ere DNO 20
,pc/c.t,) occurs.E6.Y yu WY. /T% % O v- W- 7*
REFERENCE O CNTO Vol Il 13-53 c< f p, S -g
-p l l
I l
\
- 5. THEORY OF NUCLEtR POWER PLANT OPE?ATION, FLUIDS, WD c' 4 C E 32 ANSWERS -- TURKEY 00 INT 3&4 -86/09/08-CA370 C ANSWER 5.11 (2.50)
- 3. LOCA Loss of inventory RL3/FL3 contraction /cooldown of ;:C 9
- b. RTS RTS RTS l dectuare l c. tow Fr:r presso"er low line or hiah containnent pressure.
\Srh 5L. - t{tAv r ~
[0.25 ca.3 kpYressureYk CW V) fL N4v W6- )2AM" r REFE'\ ENC 7 TPT CNTO 14-32
)l{ f( /O~E'V i
ANSWEP 5.12 (1.00) (
- a. d e c r e a s in;3 the number of H2O molecules results in a longer slowing down j length therefore neutrora travel through n. ore fuel at epitnernal energy j range decreasina the resonance escape probability, j b. A fewer number of H2O moleculet in the c o r t- results in e h; sher
.j probablity of neutrons being absorbed by fuel atomc. REFERENCE TPT CNIO R: Coro Control 2-? l ANSWER 5.13 (2.00) G 7, d{v'I#L The "TC is temperature dependent and it does not change linearly. At HCP l MTC has a value of Opcm/dec. at the core inlet (557) end -11 o,rm'de..: l-t at the core outlet 19), For calce1:tional purocce; -- d p e r.. / d e a . *- for c m ev;. noderator tenperature of 509 deg. ~ is used. Thir / clue . cmaller - than the cere avg. MTC of -5.5pcm/deg.". The Moderatar temperatur- d oe' not reach !av;. at the ec*e ,idplene. Since power peak is in the lower half of +'m core, Tavs is reached below the . core c,idpoint. (g 4 4 j) g E ' . 0,. e : Q gecEPCNCC i
' ' ** O " " ' '
kPT N O Core Control 3-4 N
, e , es <v l
t l 1 I L
{ . o 1 i 4
- 5, THEORY OF NUCLEAR POWER PLANT OPERATION, FLUIDS 7 AND PAGE 33 j ________________________________________________________ ,
THERMODYNAMICS ANSWERS -- TURKEY POINT 3&4 -96/09/08-CASTO, C i ANSWER 5.24 (1.00) i ~ Increasing the Cb increases the amount of spectrum hardening. Since the
- absorption croct section for absorption of boron decreases at higher neutron energies, the effectiv? boron absorption cross secticn decreases CO.5] as Cb increases. Theref ore the n.a g r. i t u d e of the DBW decreases E0.5].
- REFERENCE TPT CNTP Core Control 5-16 -
r S/ 0s t d
- ANSWER 5.15 (2.00) /' [#
l, 9ank overlap is used to ;<rovide a m o r r- unifor? differential CRW and ; note
- uniform aniel neutron flu
- distribution d u r i r.3 control roc n.neuvers.r/ Mey j
{A non-uniform a: .21 flux distribution could cause abnornally high pcuer peaks in the core resultinc ir feel d a n e s e Q/. 4] A uniform dierenti'l worth } always ensures that nod motion producos a ch;n3e in reactivity./0d] l REFERENCE
- TPT CNTO Cere Control 6-28 i
i i ANSWER 5.16 (2.00) 1 1.More Negat ve MTC E0.52 ) 2.fvel depletion at car e bottom EO.52
- fuel depletion is due to the BOL flu
- distribution f l u :: ped at upper i
core at EOL E0.53 , The negative MTC produceu more negative reactivity in T. h e top of +he core , ct EOL then at BOL. ' 0 52 Uf +' 'CZ~1 e gfdifv CAL I REFERENCE MM TPT CNTO Core Con ir tL S-21 , p/ - - _ 7p g (( p' CAL f 2 l O. #/ + f 6 i7 b f N l t [ncm) (/x & 'i 4___) (c j p _ 9 - V L .
a #
- 5. THEORY OF N 'J C L E A R OCWER '_A N ~ OPERATIONr FLul03 AND oAGE 34 A
M f. t' 3s C' ?,j C p.. C.a -- T ' (' C. s ' '.uC Y O D.sT.*4' T.
' 4_s /.'t'
- u. - ~'s /. /
'.,s c. ,/ r,3<2a. j - - r,.,,*.c :i roF r, ANSWER 5+17 (2.50)
- a. High rels'.ive t' l u n - causes a gre2ter react:sity charge due to CRW being c.rocorttem ; to # ' u; t i rJ f l u :- ave,
, s e u therefr e. the hiqher -
the relrtive
# 10: the a., r v a t e r the cha - s?.
(0.333 for are_'O.5 for E::o . )
- b. cr ect for the r> i d _ :. e - due to abnor;tior of ne'trans which !,sve Israer e s niqh .orobabi 'ty of causin-- # .3510n.
Aereas control roh at the edoe e absorp neutrons which h.e high probab:lity o# 1eakage.
- c. 11 hc h per wor'h When 1: serted 41 depreoccu the flu: around itselfr thit inctesso. the fle.n :n other res:ons. When 12 is inserted the f l u;,
has caen depressed therefore Its worth is lower (than its worth in an vr, rodded core;. RFFERENCE t'or th Anna RDP- .o Ts . 6.11 6.1276.19 Obe . B M/A 0 01 - 0 0 0-- M 5 . 0 2 (2.9/3.4) TPT CNTO Core Control 6-13 ANSWER 5.10 (1.50)
- a. Without RCP-driven pressuttzer spray no adequate means of n:ning loop-precsvrizer entst. (0.75)
- b. Orovides reasonable ascurance that even a "sirly rapid temperature drop will not cause problere_ with e loss of core shutdown targin. (0.75) occc cu.re u, taw Westin house background for ES-0.2 ANSWER 5+19 (1.00) remove boric acid that is precipitated on upper core surfaces 50.53 t e r rii n a t e any boiling or stea7 formation in u n o. e r head region t 4 0.53
(*
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, e l
i I r 4 j 5. THEORY OF NUCLEAR POWER c'LANT OPERATION, FLUIDS, AND PACE 35 THERMODYNAMICS ANSWERS -- TURKEY FOINT 3&4 -86/09/08-CASTO, C 4 ANSWER 5.20 (2.00) . EAD = E(Pt - Pb)/(Ft + Pb)] ' 100% or EAD = delta I / R :, pur E0.53
- Initiallyr greater power is generated in the lower seg'nent of quadrant and I EA0 will be more negative. This condition will be accentuated as <encn burns out in the lower and builds in the upper segnents. E0.752 As ,<enon builds into the lower segment while cep_eting in the upper l section due tc the neutron #1u- shift, e higher percentage of powe+ will be generated in the upper segment and EA0 will shift towards the postive value. [0.752
- REFERENCE Tc'T Op-1230C.Gi CNTO Core Control op 4-20/2? and section 9 I ANSWER 5.21 (1.00)
Ensures design margins to core linits will be aintained CO.752 under both i steady-state and anticipated transient conditions E0.252 I ! REFERENCE i TPT TS 3.2.2 i I I f , i I h
- 6. FLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 36 ANSWERS -- TURKEY POINT 3&4 -86/09/08-CASTO, C ANSWER 6.01 (1.00)
C. REFERENCE TPT SD -13 ANSWER 6.02 (1.00)
\ go gcv%
REF~RENCE TPT E0P E-1.27 1.3r 1.4 006/020; A4.02(3.9/3.8) ANSWER 6.03 (1.00) d REFERENCE Turkey Pointr Requal Lesson Plan, RCP, Fig. 16 003/000; K1.12(3.0/3.3) ANSWER 6.04 (1.00) ! C i REFERENCE Turkey Point, Drawing 5610-T-Lir Sheets ?A a n d 9's 064/000; M4.05(2.8/3.2) i i ANSWER 6.05 '1.00) i b. REFERENCE TRT SD RPS p. 23 i l l I
i f I l 6. PLANT SYSTEMS DESIGNr CONTROL, AND INSTRUMENTATION c' A C E 37 i s ANSWERS -- TURKEY POINT 3E4 - 8 6 / 0 9 / O S A S T O . C i 1 4 ANSWER 6.06 (1.00) a) Arm only (+.5 ea-i b) Arn and Actuate 3
- o. . c c c_ . .m .o. c e. r c_
{ TFT 5D103 'Stea. Dump Syste'r pp 9-16 ' 041/020; K4.id(2.5/2.8)- M4.10(3.4/3.6) ANSWER 6.07 (1.501
- c. False
- b. True
- c. Fsise REFERENCE -
TPT SD Rod Control pp. lo a 3? ! i , ! ANEWER 6.00 (1.50) , ! r I 2) Non-Urgent /+.t ya)
'a ) Urgent c) Urgent
- n. e_rt- m F. , e N, .: .
TPT SOS ' Rod Control Systen'. pp 46-68 001/010: K6.05(2.0/3.2) ANSWER 6.09 (2.00) e) 5 (*.5 ec) i b) c) 4 1 L' \ g g ' j , c- ,, ,, i
,a ,3 u t. %u . . ..
3 i 1 l REFERENCE t i C,><-F"">'. .. ' W G. TOT c' 1 a "v "a ' R. o r'. <w n *.. . o 1. - - ~ .. a : . "u 6 '. '^. .' '. , c' a ',1
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001/050; I:4.01(3.4/3.0) - I t 1 l i' - l l I l I l i l
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- 6. PLANT SYSTEMS DESIGNr CONTRCLr AND INSTRUMENTATION PACE 20 ANSWERS -- TURKEY POINT 3&4 -04/09/09-CASTO, C ANSER 6.10 (1.50)
- 2. C1,2] D rods :ove :. n
- b. 3 D RTS
- c. 3 9 rod: move i r.
Ec c e. E F.m c Nm_r e Turkey Point. H0 1005-01 ANSWEF 6.11 (1.00) i) 862 A and B (RWST +o PHR) . +.2'- ea #ce any ")
- 2) 864 A and E' (RWST isolation)
- 3) G65 Ar 8 and C ( Accuc.ula to r Isolauen)
- 4) E66 A and E: (SI Hot ten w In w ect:cn) 5I 3b3 A Und b (NHR tU D31/Cb f93? SuCblOn3 \
R E r.e m n e_ A,. r e_ n TOT T, D,T, Cm t*, '? _i 9
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- 6. PLANT SYSTEMS DESIGN, CONTROL, AND INSTRUMENTATION PAGE 40 ANSWERS - T U R K E r- 0 I N T 3&c -86/09/09-CAST 01 C ANSWER 6.18 (1.50) a) RWST :+,25 ea)
CVCS Holdup Tanks b) -Fuel ack design only allows insertion .n specific loc 3titns
-The cente'-to-center d i s t r n c <, ensures 05 !fo*" fer roent fuelr t (even if unbarated water : ~> ned)
-Porated cells are ut:1: ret 'or the fuel t a c L. s ( .5 el fer Er" tue) v " ;'
Q.c ~. C. r Q. . +tw - TPT 99d1 ' S ,c o n t Cuel Pool C o a l i. n g , c* u r i f i c a t i o n md t.' e n t i l a t i o n * , pp d-6 033/000; K4.05(3.1/3.3) fte. t n_ g -.r. e. - .9 . r, 1 .. av r> s.
- 2. Open C 10 5 t' C CPCD C10CCd C1OCCC D. C an 3tJrtIr O U t 1 tr * ;> '_* f . ; y I n 1 e t / C U ' 1 '-; t O y p li T 1 ; c t 'I p.sm.r ;- r.. p .
r i t c' .T
<1L-v: ! <3 9 - go J y ANEWEt 6.20 / 00> (( l' a, C une s 4 rt at 7 " . '5 ps law -c jer pren or_ :v e n: ;f ;r JO s ee, M .: :
g L 9 g' e . w .w
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6, PLANT SYSTEMS DESIGN, ': 0 N T R G L 7 AND I N S im: U M E N T A T Ir3 :. z g g 41 ANSWERS -- TURKEY POINT 2FC -06/09/08-CASTC, C ANSWEP 6.2: (2.00) e, Inverter is s i.7 ,cc l : e d f r o r: AC i30766) and DC (2001-49) E O . '5 ] :nd auto transfers to citernate EO.25 MCC 'A' Lt3 pene' EL' 317] E0,252,
- b. When control rods 3re in motion the trip setpoint a# the rod deviat en bistable is chansed EO.52. The change prevents f c i s c- cl arcis f r o r, spurious signal inputs EO . E .
REFERENCr TPT SD 006 47I ANSWER 6.22 ::. .vT
- o. tpa r. sa s. e '
'c . Chereinc flow decreases unt 1 etual level secr eases isolrt:n3 letdotfri.g After letdayn i n c l .i t e s orecourizer !.evel inertases until a' 02 *;
reactor t r i th"Lb s e l (w o u l d continue to increare until calid cnd PORVs rre l reltevingwbte)El.0] d-cNuf 8 /4 5 I i c. OT delte T +m i r end runbntec 2000 put c' O R V :nterlocks M . 25 e r- . ] r,: E C C P ' N " r ##~ >' S L' jg J g6 A* I Iw)a
~
ffo <# ,' / ,* j M' ** L o' 5 T-i l l l 1 r l l
_- . _ - . _ - . . . .. . ._. . . - - - . . . . . , . . . . - _ - . .. _- - _ . --. . . ~ 1 4 4 f i 1 i
- 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND PAGE 42 REDi5E5EiEEt- E 6 s T R 5E -- ~ ~--~ ~ ~ ~ -~ ~ ~ ~ ~ ~ ~
i ANSWERS - TURMEY POINT 324 -Gd/07/08-CASTO, C t i ANSWER 7.01 (1.00) 1 d 4 j REFERENCE j MNS EP/2/A/5000/16.3 i CNS EP/1//A/5000/2F3, p.7. j NAPS 1- N -I.3A, p.3. TPT EP FRP I 1 e a ANSWER 7.02 (1.00) ! b.
- REFERENCE l' NAPS 1-ES-0.2, Foldout page.
TPT Foldout page j ANSWER 7.03 (*.00) 1 1 a REFERENCE TPT ADM 0103.4, pp 13-15 I i ANSWER 7.04 (1.00) qpb Ct l v - ) "$ b REFERENCE t a c. _ g . 0 ANSWER .05 (1.00) c REFERENCE TPT ONOP 2600.1+ pp ./2 000/024; OWG-10(4.*t/c.4) l
- 7. PROCEDURES - N O Pf1 A L , ABNORMAL 7 EMERGENCY ANO DACE 43
~~ ~ EE5i5E55iE EE E5 siE 5E------------~ ~-~ ~ ~~ ~ ~ ~~~~
ANSWERS -- TURKEY POINT 384 -86/0?/08-CAST 07 C ANSWER 7.06 (1,00) 2 U
- r. crt n - . F,. c_ L. i r e _
Westinghouse back jround info for TPT EGPs, 'RCP Ta ip/ Restart *, pp 49/50 000/074; EK3,07(4.0/4.4) i. ANSWER 7.07 (1.00) i d ,i p..e-.r.- c q, c N C F
; TPT E0P-ES-0.3/0.4 000/011; Z A 2 . 0 0 ( 3 . 4 / '3 . 9 -
ANSWER ?.00 I.1.50)
- 1) NO (+.5 ea) b) -VEE f" y gc'l" '
c) NO
=.w. . c r crr. cItu Lr-.
TPT E0P + 0, CSC Etatv: Tree < , PWC-10: E0P Entry Level Condit cns /4.1/4.5) I j ANSWER 7.0? .50) i 4iChPP a I"g C. t7 .7 ". iC. sq T.'a' wT Morth Anna E" A Poldout nc - _ s TDT E-C e i I l 1 l 1 z i l t l I l L
I . o . 1 ! I j 7. PROCEDURES - NORMAL, ABNORMALr EMERGENCY AND PAGE 4c t ________________________________________________ RADIOLOGICAL CONTROL
' ANSWERS - 'UPMEY POINT 384 -96/09/08-CASTO, C i
i . 4 ANSWER 7.10 ( . 50) 12 ' E0.25 ec.: i { REFERENCE i TPT ONOP 12300 l l ANSWER 7.11 (1.00) { i HMSI 1570 pois (1500 - 1600) [ . LHSI 225 pais (150 - 250) 4 REFERENCE ! TPT E0P-E-0 p. 6 ; t I j ANSWER 7.12 (1.00) l ! < 0% level in the pres'suriner i Marsin to seturation 150 ps: E0.5ea.2 j REFERENCE 4 TPT ONOP 1509.2
+
l ANSWER , .13 (1.00) i . The c a f e;3aurd i n i t i a t i.o n signal c, u s t be reset E0.51 and then the NCC reset l { pushbutton nust be depressed CO.52, i REFERENCE I ' TPT 3-OP-057 step 4.4
)
4 ANSWER 7.14 ( .50) 1 ( l Ey depresting the 'Alarn Recet and Stop' pushoutton, i REFERENCE TPT-OP-023 EDG ' i i I 1 l l 1 : } r 1 l
'e.
4 4 . . 4 ..3 l 7. . PROCEDURES - NORMAL, ABNORMAt, EMERGENCY AND PAGE 45
~~~~Rd65UEUG5C5[~CUNTEU[~~~~~~~~~~~~~~~~~~~~~~~~
ANSWERS -- TURKEY POINT 3&4 -86/09/08-CASTO, C i 1 e ANSWER 7.15 - ( .00) . g ! Cold own
- e l REFERENCE TPT ADM 201 i
l 1 . ANSWER 7.16 (1.00) 1 1 1) Heat sink (+ 15 "or CSFr +.1 for correct order)
- 2) Intestity 1 3) Containment i 4) Inventory REFERENCE E0P-F 0, ' CSP StEtus Trees
- i ANSWER 7.17 (1.00) (( /8 -5 5
! 6 v j 1) Criticality plannrs within 4 hovrt (+ 25 ec) l 2) Boron Concentra+.on 300 rpm
- 3) Trip ues f r o r- 40%
- 4) Equilibrium enon culuted prior to itip
. REFERENCE
- TPT GP-0202.2, pp 15 001/050; PWG- (3.7/3.7)
ANSWER 7.18 (1.00) I j An '3 I p u n p (+.25) takec a suction on Loop C (+ 25) via the W .ystem , and its HXer:. (+.25) where 'tt cooled by CCL :+ 25) j REFERENCI TPT ONOP-050, pp 5/6; Tri TS 9 3 .10 . ,' 005/000; K 3 . 0." ( 3 . 2 / 3 . 6 ) l t i I i i I._._._-._,___________ _ _ . _ .__. _ _ _ _,___ _ _ _.~ _.-.,_.
(
- 7. FROCEDURES - NORMAL. A E:N OR M A L r EMERGENCY A >iD DAGE 6
~~~~5565E[UU5CdE~C6ti??5[~~~~~~~~~~~~~-----~~~~~~
AN3WERS -- T U R !' E Y o0 INT 314 -86/09/08-CAST 0r C i i ANSWER 7.19 (1.50)
- 1) Sound Containment Evacuats an Alarm + 23 ea)
! 2) Stop CNTMT purse supply c r p
- 3) Stop *
- s ~ h a u s t.
IT 3 41 Close the CNTMT !iijzrunent A;r 0 ->d Valves
- 5) Close CNTM y;r g e _,Upply isalation valvec
- 6) Clone '
enhauct c; r e c o r > j r c [FT bbbh 1600F. 2- pp 2/3 i o n, c. ./---n e, a ; o y r1_1
~ . .i r ". . n : . .* )
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ANORER 7.20 ( M O) RCP Thernal 'c a r r i e r CCW cutlet (FCV t:6) Oect:ng CCW outlet (MOV '30) CCW aupply inci_rions (MOVc 716A 2nd 7165) cc /d VL E0.25 es. vcive) c9 _% c 6 d/ //v" REFERENCE TPT SD 62 .n o 33 ,
.s ANSWER ~,21 ( u 0) i if runbect hcc not occur v er - un turbine baci to 70% (+.6) p Q o c, control in manua, .
'4 .ae
-s ,i c o n. ' r n ' --
'ro r u n t m. borom (+ v . Ly' Sbb O [#' i _ 5, /,
REFE7ENCc TFT ONCP 1600.1, pp 9/10 EPE 003; PHC-11(a.2/C.a) I ANSWER 7.Z~ (1.00) The operatar shoulc a.ain i n ECA-0.0 ,ine' +he r '~ _ 1r e urttten an the , P r e a.i s e thet :- t leest one E -- b u s 1. encr3 red. 1 I 6
)
. _ . _ - _ _ - = - . . - _ _ _ _ _ _ _ . _ _ . - . _ . _ , - - _ . _ . _ _ . _ _ _ _ _ _ _ _ _ -
i ? r i f , 7. PROCEDURES - NORMALr ABNORMAL 7 EMERGENCY AND PAGE 47 [ t ________________________________________________ j RADIOLOGICAL CONTROL + 4 ____________________ t ANSWERS -- TURKEY POINT 3a4 -86/09/03-CAST 07 C i r l REFERENCE I West. backsrcund info. for ECA-0.0 ! l I ANSWER 7.23 (1.00)
- 1. SI clow is a significant contributor to any cold les temperature decrease E0.52
- 2. It can also be a significant contributor to an overpressure condition if the RCS is intact. [0.52 i
REFERENCE , i West, background info. for FRP-P.1 ; 2 l l ANSWER 7.24 (1.00) l AFW Train i shall consist of AFW pump (s) A E C E0.253 aligned to take a i suction from the CST CO.25] and discharge to the S/G through cCV CV-3-2816, i 2017, and 2810 E0.252. The steam supply for the AFW pumps shall be from l MOV-3-1405 and 1404 CO.253 (The train will also include all piping and i valves and controls necessary to provide these independent stean and water flou pcths) [ REFERENCC i TPT 3-0P-075 p B (4.0.1) ANSWER 7.25 (1.00y
- p. u j>7(
2/4 channels (N41-N44) indicate inside the def;ned target band for the ! respective channel, f REFERENCE ! TPT ONOP-100E.6 i ANSWER 7.26 (1.00, l
' 2 hours E0.25: An infor".ai turnover mnt be complete.t prior to 'he operators departer_ E0.252. Note chanseove- In operators 103 prior to departure EO.25] and u p a r. return CO.25~.
REFERENCE TPT AP 0103.2 pp. 15 (0.2) o l l i I l , 1 t 4
_ ____ _. t i 1 i. G l 7. PROCEDURES - NORMAL, ABNORMAL, EMERGENCY AND ' AGE 48 i l RADIOLOGICAL CONTROL . A N S W E '% S -- TURKE't POIU* 3&4 -96/09/08-CASTO, C E ( 1 ANSWER 7.27 (1.00) l . An SI will automatically be intitic+ed by high z' >a- line - stem generator diff. presrure if this is exce: d e r, . 1 c.t
= _ .
F r R, P_.N r_,r_ - l TPT CP-0202.1 p. Y ? s i i ANSWER 7.28 (1.00) l 4 Pullin2v the control powe" fuses on ' / ': enannel will result i. o -' reactor t i j trip. Ecaf i ! R E F E R E N C:~ ! TPT OP 0205.1 p. , 12 ( . I j ANSWE- /.29 (1.00: A reactor . rip may recolt E0.72 ac 2 1 5 ". level tenal has been introduced into the tris. logic E0.33 r, c
.._ F p_..s r, te xke c_
, TPT ONOP 003.7 pp . l l ANSWER 7.30 ( ,00) l 4 The turbine is trip;'. 'o that
, 6. h e h e a c, sink will be maintained a :, lang 2; poscible EO.5: on e totcl loc o* feedwater ATWB E 0 . 5 .] l t
l REFERENCE 2 l Westinghouse SacP3round Info. on -RP-S.1 } p ( I 4 d J I a 1 1 I a k 4
} .
_re- __ ._w MvW
e o i l G. ADMINISTRATIVE PROCEDURES, CONDITIONS, AND LIMITATIONS PAGE 09
. ANSWERS - - - TURKEY c'0 INT 3 ?. 4 -86/09/00-CASTO, C i
ANSWER 3.01 1.00) > h. REFERENCE TFT AP 0 *. 0 3 , ~3 2 ANSWER 8.02 # 1.00) i (b) i i REFERENCE i EPIP '3.02 and 3.03. T;T EP 20104 pp e, . PWC-36: E-P'an .2.?/4.7) . i 4 ANSWER E.03 (1.00) i J YJ. {.
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- 8. ADMINISTRATIVE t'ROCEDURES, CONDITIONG, AND LIMITATIONS ' ACE 51 ANSWERS -- TURKEY c' 0 IN T 3&4 -86/09/08-CASTO, C REFERENCE TPT AP 0103.36 pp 2.
ANSWER 8.11 (1.00)
- 2) : or 4 ( + ') ea) b) 3 c) i REFE9ENCE PT AP 0103.4r ;-- 34?
PWG-14* T e g 31 rec / C l e r; r. < , c e h ac < dur es ( 3. 6/4. 0 ) t, y r;. n. r p p3.., ( t . o n. -) PS-N
EFERENCE TPT ADM 503 ANSWEP 9.13 ti,00)
- b. Charr'el F uric t:.orn: 1 Test
- r. -c.r r,e c.. .> ka.r r J. r>I +I T.se- i,-,,
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8, ADMINISTRATIVE FROCEDURES, CONDITION 0r AND ' IMITATIONS PACE 52 ANGWERS -- TURKEY POINT 314 -86/09/0C-CAST 07 C ANSWEF. c3 .15 (1.00)
- a. 1
- b. 1
- c. 3
- r. .
a m
- e. :,
REFERENCE NA 'J182 is table 6,2-1. TPT TS Table 6.2-li TPT AF 0103.2, pp la FWG-23: S t a f' f i r g / A c t i v i t i e s (2.9/3.*5) ANSWER 8.16 (1.00)
- 1) Plant Si> p e r v i : o t - N e c l e a r ( P S - N '; (+,5 ea)
- 2) Nuclect Match Engineer (NWE)
R E F R E N C E TPT AP 0103.4 pp 7 PWG - 14 : Taggtng/ Clearance frocedures(2.6/4.0) ANSWEP D.17 (1.00) Oreak er and 'Onduheel EO.S ea.2
..,.,_n_,v.,,_
n r r ::. u , T P I' A* 0102.4 pp 4. ANSWE9 0,10 ',,00) WE' 3.0 r r1 e. t - Skin 7.; rem /qte REFERENCE 10 CFh 20
_ _ _ _ADMINISTRATIVE B. _ _ _ _ _ _ _ _ _ _ _ _ _ _ '$' D C E D U R E S , . C O N D I T I O N S r AND LIMITATIONS OACE 53 t.NSWERS -- TUP 4EY POINT 3&S -86/07/09-CAST 07 C , ANSWER 8.19 (1.00) f d. REFERENCE TFT TS 3.1.1.e ANSWER 2.20 (1.50)
- 1. Classification er vent t 2, Decision to not1'y state and loccl c u t h o r i t i e r_ !
- 3. Protective action r ec ommer.da t l an 3 !
REFERENCE TPT EP 201C'1 pp 2 ANSWER 8,2 ( .50) once/ shift ; REFERENCE TPT A0 0103.2 pp 12. Wo L[ 7 7 _ 9 - )i
- i ANSWER O.22 (1 50) h !
- 3) 34 and 30 and either 44 or 47 4160 'V buses (4 .5 ea) b) 3 of 4 400 VAC Load Centerc c) d o t' 6 S a t t o r ij Charjore l
REFERENN " TPT TS 3.7.1 'l 062/000;PWG-5(3.0/4.0) i j i i f t b I L r I
- 3. ADMINIGTRATI.!E oPOCIOURES, CONDITIOh9, c, N D LIMITATIONS OAGE 54
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- 1) I Q 'J 7 - $78,2 d 0 -J' (+.I '
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- 2) Pzr Pretsure 2220 7Eic
- 3) R; Coolant claw 260,500 C 5 'd p r e r- t.. .r -,g. r: ew
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- 8. ADMINIS TR ATI'JE PROCEDURES r CONDITIONS, AND LIMITATIONS PAGE 55 ANSWERS -- TURKEY POINT 3&4 -86/09/03-CA9TO, C ANSWER 8.27 (1.50) a) 1 hour is the tir.e limit (+.5) b) No operations which could cause dilution are ellowed (+.5 ee; Core outlet temperature must be 10 des F belou saturation REFERENCE TPT TS pp 3.4-2a 006/050; PWC-1(3.8/4.0)
ANSWER 9.28 :1.00) With Tenperature ' 500 degreese .he release of activity to the environment due to a SGTR is precluded '+.3) since Psat is ' SG DORV lift setpoint(+.7) PEFERENCE TPT TS B3.1-6 002/020; PNG-5(2.9/4.1)
P. O. Box 14000. JUND CE ACH FL33:06MW l **
- ENCLOSURE 3 4
SEPTET q 1 a'* ~ L-86-382 Dr. J. Nelson Grace Regional Administrator, Region 11 U. S. Nuclear Regulatory Commission 101 Marietto St., N.W., Suite 2900 Atlanto, GA 30323
Dear Dr. Groce:
Re: Turkey Point Units 3 and 4 Docket Nos. 50-250 and 50-251 Operator License Examinations This is to confirm the technical comments presented to your staff of the exit ' interview following the examinations administered to proposed and current operators at Turkey Point on September 8,1986. These previously discussed technical issues and several odditional technical comments may beer significantly on your evoluotion of these examinations; occordingly, they are formally transmitted herewith for your consideration. - - Also, as your staff is aware, FPL has identified a number of concerns with respect to the examinations which go to their basic validity and which we believe should be reflected in your final action on the above-mentioned examinations. We are prepared to discuss these matters with you at your earliest convenience. As you are also aware, FPL has previously taken steps to improve our operator training program and these programs have now been accredited by the National Nuclear Accrediting Board. These training improvements and the resources expended in support of these improvements cannot be totally effective if the testing process that our operators are subjected to is not valid. We look forward to discussing these issues with your staff. Very truly yours, C.O.W Group e President Nuclear Energy COW /PLP/cvb Attochment cc: Harold F. Reis, Esquire
-gf70/gp/-- 32g_ PEOPLE CERVING PEOPLE
~ .
09/11/86
'
- Pcgel s
NRC Exam Section 1 4 QUESTION RO 1.03:(SRO 5.01, SRO Requal 5.02) A reactor has been operating at full pwer for three months when a manual
- i. reactor trip occurs. All systems are operational and the steam dumps are immedia'tely placed in the steam pressure control mode. Ten minutes after the reactor trip, all RCPs are tripped. Twenty minutes after the reactor trip, Loop 1 RCP is jogged momentarily. Which set of traces (a - c) on figure #174 most closely represents the previously described events?
i
RESPONSE
We request that answers "a" or "b" also be accepted or delete question. i Answers "s." and "b" c.orrectly show Te increasing at the beginning of the I transient. In addition, the poor quaity of the trace reproduction made it difficult ! tointerpretthe ATbetweenTe and thermocouple readings. .
~
Discussion with Westinghouse confirme'd E'at none of the traces given in the i question is truly representative of what should actually occur.
REFERENCES:
l Telecon with Westinghouse on September 10,1986 f l l i I l * @.5/cas
l 09/11/86
. . Pcge 2 NRC Exam Section 1 QUESTION RO 1.04:(SRO 5.02, SRO Requal 5.03, RO Requal 1.04)
For each of the following parameters compare a Core Thimble Cell to a Normal Core Cell and indicate which of the two;has the higher value. (rated conditions. average values)
- 1. Total power production
- 2. Powerdensity
- 3. Enthalphy rise
- 4. Mass flow 5.DNBR
RESPONSE
We request that this question be deleted from Requal Exams.
\
This topic was not covered in the Accelerated Requal Class. Lesson Plan in Accelerated Requal Class did not cover this t;opic as shown on reference.
REFERENCES:
Instructor Lesson Plan No. 0017-OL, Appendix A, Page 2, Rev. O,03/31/86
*RI-5/cas
TESTITEM ANALYSIS SHEET RO I.10 (SRO S.071/1.5 pts. Question # / Point Value: A reactor which has been operating at full power tEOLi trips Question: due to a[ Loss of All Offsite Power. Natural circulation condition:p have been established and 4 team dump to conden-er is operational. Steam Generator lesels/ pressures are at no. load stable values. Core decay heat generation howes er, is exceeding the free convection heat transfer rate capability. EXPLAIN the thermodynamic principles which will cause fuel element temperatures to esentually reduce to lower values (assume a relatively constant heat generation rate within the fuel) Answer: Since free convection heat transfer rate under subcooled conditions increases as a function of the available temperature difference between wall and bulk fluid (delta T) [0.251 the heat transfer rate to the Rx coolant in the core area will increase (0.25] causing an increase in core exit temperature {0.251 increasing the available natural circulation driving head [0.25) whicp will cause an increase in mass flow [0.251 thereby increasing the convective heat transfer capability of the RCS. The higher , mass fiow will also cause [0.25] a corrective decrease in fugl e.lement temperature. ,
Reference:
TPT CNTO Vol ll 14 26 K/A EK 1.013.7/4.2 Technical Review: Inaccurate information stated in stem of question.
- 1) Steam dump to condenser can not be operational during loss of all offsite power. CW pumps will trip, condenser vacuum will decrease, locking out the condenser steam dumps.
- 2) Increasing steaming rate will also increase driving head.
- 3) Higher mass flow resulting solely from increased coolant temp will only stabilize fuel temperatures, not cause a
" corrective decrease" Construction Review: No comments Relevancy Review: No comments K& A Review: Insufficient K/A reference Recommendation: Delete question.
- RI-5 dsp 09:1S/86 Rolllo
~ ~
09/11/86 ' Pcge 3 NRC Exam Section 1 QUESTION RO 1.12:(SRO 5.09, SRO Requal 5.06) Restrictions on F(Q)(T) limit include penalties due to uncover and reflood rates, post-LOCA. Give one other basis for gore height restrictions on F(Q) (T) and j explain where and why it is restrictive. *
RESPONSE
We request the answer key to be expanded to accept answers that concern fuel temperature. clad temperature and DNB during SB LOCA and discussion of K(Z) curve. F(Q) was taught in Accelerated Requal as a limit on fuel temperature rise to protect the clad.
\
e
- R1-5/cas .
09/11/86 . .- Pege 4 NRC Exam Section 1 QUESTION RO 1.13c:(SRO 5.10)
- c. Explain why curve "C"is valid at < 15% quality and not at > 15% quality.
RESPONSE c: I We request that the answer key be expanded to accept an explanation of analysis limitations to generate the curve.
REFERENCES:
Thermodynamic Principles U, page 13-54, 55 and 56, Westinghouse copyright 1982. s O e 4 08 80 t
- RI-5/cas
TESTITEM ANALYSIS SHEET RO t.13 SR0 5.10 /1.5 pta. Question # / Point Value* Refer to fleure
- J57."Tave vt Power"and answ er the rottom mg:
Question:
- a. On the graph curse 'A' hounds the masimum operstme I,wn ten 5perature at a gisen system pressure ter a particular reacter poner E spiain the basis for graph'A*and w hy it hJ4 a negatis e slope.
- b. Graph 'B' ensures that two adverse conditions . ire not esceeded. State these tw o conditions.
- c. Explam why curve 'C' is valid at < l54 auslity and not at >l54 quality.
Answer; a. This curve is based upon preventing hot leg temperature from reachme a saturation temperature as power increases the diflerence between Th
& Tc increases.10.251 In order to keep Th belom saturation. Tas g must decrease with pom er(0.251.
- b. To mamtain mimmuni DNBR10.251 Ensures that the avg. enthalpy at the vessel esit does not exceed the enthalpy of saturated liquid. [0.25)
- c. At higher pressure. a higher Tavg is necessary for 15% quality 1.251 at low er pressures DNB occurs at 15%. At higher pressures, the quality of i a ater may be >20% before DNB occurs.10.251 Referenee: cNTo voint i343 .
i , Technical Review: Ro i.t3c: The an er key does not address the question. , Curve "c"is valid at < 15% quality and not at > 15% quality because the WRB-
! correlation used to predict DNB only applies to fluid at less than 15% quality.
Above 15% quality,the WRB.1 correlation is not valid. Construction Review: Part 2 is mi.iending in that it rerers to masimum operating ioon temperature", but craph labet is Tm vs. pom er. Part 'c' Figure doesn't apply to PTN < ES-20t I spg 5 of 8); Westinghouse told trainees concept has no a pplicability to PTN; double jeopardy question (ES-202 E 13,ips 4 of 6). Thorndike and Hagenipg 95p. t Relevancy Review: Not relevant for RO candidates. NRC Exammer Standard ES-202," Scope of Written Examinations Admmistered to Reactor Operators- Power Reactors". ( I Rev.1,10/1/84. Part E.1 states that Tech Spec questions for reactor operators should be conceptual in nature, which does not include specific basis explanation. i Page 3 of 6, ES-202). K&A Review: No wA reference [apand Answer Key (per previous submittal) or l Recommendation: Deiete entire question rrom Ro esams. Delete part "c" from SRO exam.
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09/11,86 . .- Page 5 NRC Exam Section 1 QUESTION RO 1.14c:(SRO 5.11)
- c. State three possible initiation signals which may initiate SI upon a steam line break accident. i [0.75]
RESPONSE c: We request that the answer key be expanded to accept Hi Steamline Flow with Lo Tave or Lo S/G Pressure
REFERENCES:
Logic diagram 5610-T-L1, Sheet 19, Rev. 5 i l .
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. 09/11/86 Pcg26 NRC Exam Section 1 QUESTION RO 1.16:(SRO 5.13, SRO Requal 5.09, RO Requal 1.09)
Explain two reasons why the computed moderator-only power defect underestimates the actual defect. dud to redistribution at BOL, assuming a calculational value of MTC of-4 pcm/deg. F. (HFP, Cb = 1200 ppm]
RESPONSE
We request the answer key be expanded to accept a general discussion of MTC, Power Defect and redistribution due to the large percentage of Operators who had difficulty in understanding the question.
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. .- Page 7 NRC Exam Section 1 QUESTION RO 1.19:(SRO 5.16, SRO Requal 5.07)
Refer to figure # 363, discuss the two factors which afTect the Axial Power Distribution at EOL and result in a relatively flat power distribution.
RESPONSE
We request the answer key be expanded to accept the affects of redistribution and flux burnout in middle of core since Turkey Point is in Fuel Cycle X and our flux is slightly positive at BOL.
REFERENCES:
Telecon with Turkey Point Reactor Engineering on September 9,1986.
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. 09/11/86 Pege 8 NRC Exam Section 1 QUESTION RO 1.21a:(SRO 5.18) a.Why is this action necessary during Natural Circulation Condition (.75) i
RESPONSE
- a. We request the answer key be expanded to accept responses that address non uniform mixing of the RCS in general, notjust the pressurizer.
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l 09/11/86 Peg 2 9 NRC Exam Section 2 QUESTION RO 2.03:(SRO 6.02, SRO Requal 6.02, RO Requal 2.02) Which of the following statements correctly describes the RHR System liraup when HOT LEG RECIRCULATION is 9stablished? (assume both trains of RHR are available)
- a. Both trains are used to supply hot leg recirculation exclusively.
- b. One train is used to supply hot leg recirculation and the other train is used to continue cold leg recirculation.
- c. Both trains supply both hot and cold leg recire simultaneously.
- d. One train is used for hot leg recire and the other train is put in standby (i.e.,
recirculates from RHR HXer outlet to RHR pump inlet).
RESPONSE
We request the answer key be revised to reflect"b" as the correct answer. i
REFERENCES:
EOP-ES-1.4, Steps 1 and 2 dated 07/27/86
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09/11/86 Pcga 10 l l NRC Exam Section 2 QUESTION RO 2.11:(RO Requal 2.06) List the 6 essential safety related loads served by the Component Cooling Water System (redundant components like CC heat exchangers are one load). l l RESPONSE: l l We request the answer key be revised to accept " Pass Heat Exchanger" and delete SFP Heat Exchanger l j
REFERENCES:
i SD 040, Rev.1-7
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09/11/86 Pcge 11 NRC Exam Section 2 QUESTION RO 2.12a:(SRO 6.13, SRO Requal 6.10, RO Requal 2.09)
- a. Refer to figures #397.1 and #397.2 Reactor Coolant Pumps. List all interlocks which must be met to start an Oil Lift Pump (OLP).
[0.51
RESPONSE
- a. Figure 397.1 requires breaker to be closed, but 397.2 does not. We request that no penalty be levied for a response that does not include " Breaker Closed".
REFERENCES:
Figures 397.1 and 397.2 i
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09/11/86 Page 12 NRC Exam Section 2 QUESTION RO 2.13 a and b:(RO Requal 2.08)
- a. Refer to figure #398 Heater Power Distribution. State the purpose of the Current Transformers (CT's) wrapped on the heater supply lines.
- b. How are small electrical grounds ('e.g. grounds which do not trip breakers) detected / indicated on Pressurizer Heater strings?
RESPONSE
- a. We request the answer key to be expanded to accept the response "CT's supply any indication meter."
- b. We request the answer key be expanded to accept the response " annunciator in Control Room for 480 L.C. Ground." In addition, there is no ground detection instrument for pressurizer heater strings. We request that alternate answers for ground detection be accepted.
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REFERENCE:
Training BriefNo.64,06/15/85 p i I l ! *R15/cas
TESTITEM ANALYSIS SHEET Question # / Point Value: R0 2.16/ 0.50 pts. Question: Refer to figure *401 Charging Pumps. STATE the force <si 1 which mdintain seal water flow through the packing of the ! charging pumps. Answer: (thermally induced) natural circulation and head of water form seal tank [0.25 eachl
Reference:
TPT SD 12 Technical Review: Seal water flow through the packing of the pump is maintained by the static head of the head tank and has nothing to do with thermally induced natural circulation. Construction Review: Answer not relevant to question, answer key does not answer question. ES-107 C1,(pg.1 of 3), Wood (pg. 46), Thorndike & Hagen , (pg 79), ES-202 E10 (pg. 4 of 61. IFlO - i . ,
- n. . .
Relevancy Review: No comments. K&A Review: No K/A reference Recommendation: Accept seal water static head as answer. {
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Roll-37
09/11/86
. .- P ge 13 NRC Exam Section 2 QUESTION RO 2.19 a, c and e:(SRO 6.17, SRO Requal 6.12, RO Requal 2.12)
For each of the following abnormal piqnt conditions state whether or not AFW pump 3A would inject into the Steam G6nerators at rated conditions and for each condition in which the AFWP does inject state all adverse consequences of the given condition (assume a valid start signal occurs). Consider each case separately.
- a. The discharge flow transmitter on AFWP 'A' has a failed "high" high pressure tap. (prior to start)
- c. AFWP 3A Trip & Throttle valve trip solenoid has an open circuit.
- e. The main oil pump shaft fails.
RESPONSE
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- a. We request the answer key to expanded to accept "will inject" with an accompanying explanation on a case,by case basis. The questioh was confusing to the Operators since there is no discharge flow i.ransmitt'er as such for"A" AFW pump.
- c. We request the answer 'aey be expanded to accept "will not inject" with an accompanying explanation. There was insufficient information given 'to determine the affects of an electrical open circuit on the T&T valve trip l solenoid.
- e. We request the answer key be expanded to accept "will inject" since the pump will not trip. The pump will run until it seizes and fails.
REFERENCES:
Operating Drawing 5610-T-E-4062
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. 09/11/86 Pcge 14 NRC Exam Section 2 QUESTION RO 2.22: (RO Requal 2.14)
Refer to figure #409 " Basic CVCS Flow Balance". For points 1 - 5 state the design values for flow (gpm) at each point.
RESPONSE
We request the answer key be expanded to accept 45 gpm to 120 gpm for point I due to varied LTDN orifice configurations possible. We request the answer key be expanded to accept the value of 25 gpm for thermal barrier flo.w (point 5) which is the value of CCW flow through the thermai barrier. Students asked the proctor if they wanted the CCW flow and the proctor said "yes".
REFERENCES:
Turkey Point FSAR, Table 9.2-2 , l, , , . . SD008, Rev.1-19
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- 09/11/86 Page 15 NRC Exam Section 3 QUESTION RO 3.08d:
Match the interlock descriptions in Column A with the appropriate logic required to cause rod withdrawal to be blocked in, Column B. (column B items may be used more than once) COLUMN A COLUMN B
- a. Power Range High Flux @ 103% power 1. 1/2
- b. Overtemperature Delta T rod stop 2. 2/2
- c. Intermediate Range High Flux 3. 1/3
- d. Power Range Rod Drop 4. 2/3'
- 5. 1/4
- 6. 2/4
- 7. 3/4
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RESPONSE: .
- d. We request the answer key be revised eflect"5" as the correct answer.
REFERENCES:
Operating Diagram 5610-TL-1, Sheet 17
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. 09/11/86 ;
Page 16 ! l NRC Exam Section 3 l QUESTION RO 3.09a: For each set of plant conditions listed below STATE all functions (of 1,2 and/or 3) which would be generating a rod movegnent signal and STATE the response of Bank D rods (in, out, no movement) to this signal. Bank D at 200 steps.
- 1. Bank Selector Sw. 2. In-Out-Hold Lever 3. Plant Condition
- a. Manual IN Urgent Failure
RESPONSE
- a. We request the answer be expanded to accept" Rods Do Not Move" since this is true for an urgent failure in a logic cabinet.
REFERENCES:
i Control System Diagram 5610-T-D-12A, Sht,et 1 of 1 .-
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. . 09/11/86 Pcge 17 NRC Exam Section 3 QUESTION RO 3.14a:(SRO 6.20, SRO Requal 6.09, RO Requal 3.09)
Assume the following CCW pump alignments: B&C pumps are racked in andin AUTO B pump is running A pump is racked out and open
- a. If'B' pump received an over current lockout what signal (s) wculd auto start
'C' pump AND at what time would it start?
RESPONSE
We request the Operators not be penalized for not including the low pressure setpoint in the first part of the question. The setpoint appears in the answer key but was not asked for in the question. i .
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. 09/11/86 Page 18 1
NRC Exam Section 3 QUESTION RO 3.15:(SRO 6.21, SRO Requal 6.08, RO Requal 3.08)
- a. For the Unit 3 Rod Position Indication (RPI) power supply, describe the supply to the DC power system, inkluding both normal inverter supply and alternate supply. Include all auto'matic features associated with these two sources.
- b. The Rod Deviation Monitor generates a ' Rod in Motion' signal. EXPLAIN the basis for this signal AND the action (s) which are initiated by the signal.
RESPONSE
- a. We request the answer key be expanded to accept a drewing (sketch) of this system. It is our understanding that the Examiner stated that a drawing was acceptable.
- b. We request the answer key be expanded to accept " Alarm at 12 steps Stationary,24 steps moving" s!nce this demonstrates the setpoint change as stated in answer key. -
REFERENCE:
SD6, Rev.0-12 . l l
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l ! . . 09/11/86 Pcge 19 NRC Exam Section 3 QUESTION RO 3.16b:
- b. Exactly how does Steam Generator level flow controller FC 478 operate the Main Feedwater Control Valvel Include motive force (s) and signal conditioningequipment.
RESPONSE
- b. We request the answer key be expanded to accept instrument air as a motive force. Question was read as" motive force to move valve"
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. . 09/11/86 Page 20 NRC Exam Section 3 QUESTION RO 3.18b:(SRO 6.22, SRO Requal 6.07, RO Requal 3.05)
Unit 3 is operating at full power, all control systems in auto, Pressurizer level channel 1 (LT 459)is selected. Answer the following:
- a. Would a common failure on LT 461 and LT 462 causing both to read maximum result in a reactor trip? (yes/no)
- b. The reference leg for LT 459 (PRZR level) develops a significant packing leak causing the reference leg to drain. State all the auto actions afTecting the Pressurizer which would occur as a result of the failure.
- c. List all functions of pressurizer pts 455,456 and 457.
RESPONSE
- b. We request the answer key be expanded to accept " backup heaters on." In addition, we request the Oper'ators not be penalized for not including the water solid condition written in the answer key since the question aslied for auto-actions and did not refer to a tranjip,nt description over time. 5
- c. We request the answer key be expanded to accept " reactor protection and SI" as stated in SD009 and also accept "Hi and Lo Pressure Trip, Lo Pressure SI and associated alarms."
REFERENCES:
SD-009, Rev. 0-40 5610-T-D-16A, Sheet 1 of1
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09/11/86 Pcge 21 QUESTION RO 3.19 Refer to figures 82.1,.2: l i
- a. What is the purpose of the Droppek Rod Normal / Reset / Bypass or Switch !
on the Power Range A drawer?
- b. What automatic actions (if any) would occur as a result of a " loss of detector volt alarm"on the Power Range A drawer?
- c. State the purpose of the gain switch on the Power Range B drawer.
RESPONSE
- b. We request the answer key to accept
\
- 1) Blocks Auto Rod Withdrawal
- 2) Initiates a Turbine Runback Signpl . ,'
Students were led to believe that the P.R. Detector lost its hi voltage supply, which will cause the detectors output to fail low, therefore tripping the NIS 5% pwr decrease 5 seconds bistables which generate the above listed signals. .
REFERENCES:
- TP System Description #004 Pg. #46 & #47 TP Fact Sheet #012 TP Fact Sheet #003
- TP Drawing 5610-T-LI Sh. #21 i
i i *R15/cas
Pcge 22 QUESTION RO 4.04 (SRO 7.04) Which of the following statements describes the correct usage of the Critical Safety Function (CSF) Status Trees while performing EOP-E-0 " Reactor Trip or Safety Injection"? -
- a. The CSF Status Trees are ONLY monitored when EOP-E-0 directs.
Awareness of Red Path Criteria is required at all times, but the CSF Status Trees are monitored ONLY after it is determined that SI can NOT be terminated.
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- c. Monitoring of the CSF Status trees commences as soon as the immediate action steps are completed.
- d. CSF Status Trees are required to be monitored as soon as the procedure is entered and a valid SI is determined to have occurred. .
- RESPONSE:
i We request the answer key be expanded to accept"a" or"b" The question is worded "while performing EOP-E-0" which makes "a" correct also.
REFERENCE:
" Users Guide for T.P. EOP's and Background Documents" 19635:4 Pg. #16 l *R1-5/cas - - - . . - - - - , . - - - . , , , - - . - , . - - - . - - , , - - . .-. . - , , , , , _ , . , - . --..-,,-n--,, _. ,,- ,,- , . , - - , . , - - _ - _ - , .,
. . 09/11/86 Pcge 23 NRC Exam Section 4 QUESTION RO 4.16:(SRO Question 7.15)
What plant condition is assumed in the valve / breaker " Normal" position designation for the Operating Procedure! alignment sheets?
RESPONSE
We request the answer key be expanded to accept " Mode 1,"" Mode 2" or " Power Operation." The question did not state as per 0-ADM-201 and the Operators are experienced in the use of alignment sheets for power operation.
REFERENCES:
OP-0202.2, Table 1,5/1/86 s S e l l l
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- Page 24 NRC Exam Section 4 QUESTION RO 4.19:(SRO 7.20)
List all the valves which reposition as a result of a Phase B ("P") isolation signal.
RESPONSE
We request that the answer key be expanded to include " Containment Spray Pump Discharge Valves"
REFERENCES:
Drawing # 5610-T-E-4510 Sh.1 of 2 .,
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. . 09/11/86 Pcge 25 NRC Exam Section 4 QUESTION RO 4.20:(SRO 7.21) -
With rod control in automatic while at 80% power, what are all the immediate~ operator actions if a single rod drops !(assume no rx trip) as stated in ONOP' 1608.1," Full Length RCC Malfunction"?
RESPONSE
We request that the answer key be expanded to include " Verify Turbine Runback" as per ONOP 028. f
REFERENCES:
ONOP-028, step 4.5.2,03/28/86 ; i . P
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s i t s
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09/11/86 Pcge 26 NRC Exam Section 4 Q ESTION RO 4.24:(SRO 7.25, SRO Requal 4.17, RO Requal 4.17) Define "Inside t.he T,arget Band"in accordance with ONOP-1008.6, ' Operations outside the Target Band'. !
RESPONSE
s Expand Answer Key toinclude"iS% ofTarget" e
REFERENCES:
ONOP 1008.6 Pg.1 Seet. 3.2.2,01/29/82 i I s 6 e
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- - 09/11/86 Pcge 27 NRC Exam Section 7 QUESTION SRO 7.19 Besides required notifications, what are the immediate operator actions if you are on shift in the control room and the refueling! supervisor in the containment reports they dropped a spent fuel element in containment?
RESPONSE
Request that the Answer Key be expanded to accept the following as an additional answer:
- 1. Sound ContainmentEvacuation Alarm
- 2. Initiate Containment Ventilation Isolation i
REFERENCES:
i E-0, Page 6, Step 12 i l [ l l t
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- - 09/11/86 Page 28 NRC Exam Section 8 QUESTION SRO 8.22(SRO Requal 8.15) List the MINIMUM requirements for each of the necessary electrical systems listed below in order to conduct a reactor startup 4n UNIT 3, assuming Unit 4 is shutdown. a) Unit 3 and 4 4160 KV buses b) Unit 3 480 VAC Load Centers , c) Battery Chargers
RESPONSE
We request that the Answer Key be expanded to accept "4 of 4 4160 Volt Buses" as an additional answer to meet the requirements ofTech Spec 3.4.1.A.4
REFERENCES:
\ . Tech Spec, Page 3.4-1 4-OP-062, Pages 4 and 24 , ,.'.,
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