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100 120 CORE FLOW {% RATED) (Rev. 12 1/03) PERRY NUCLEAR POWER PLANT Typical Design Power/Flow Map Standard Power/ Flow Region Figure 15.0-1
100 SCRAM WORTH AT 100% = -$37.05 0.43 0.9 3 r.43 t. 9 3 2,43 2.93 3.43 S C R A M I N S E R T I O N T I M E ( S E C. ) ( R e v. L 2 1/ 03) f E = (J uJtr (r (J v, r'D<\\ \\ CffiM PERRY NUCLEAR POWER PLANT I \\ ) a /
- {_H Scram Reactivity Characteristics
( REDY ) F i g u r e 1 5. 0 - 2
tr z
- UJotr, tu g
zo F6o A oo(r Jotr Fzo() SCRAM INSERTION TIME (SEC) (Rev. 1"2 r./03 ) I t--6J I di"E PERRY NUCLEAR POWER PLANT t v / l \\.# Scram Ti-me Characteristics F i g u r e 1 5. 0 - 3 CONTROL ROD DRIVE SPEED ROD POSITION % INSERTION T I M E sEcoNos 0 1 1 0 40 75 0.100 0,138 0.317 o,874 1.620
=.n G,Ie 3rr J Err .tHf; J b Ll lrJ 8= 3E Glrl G* ct r\\t e (J trJ UI Fi-I I t5. rr d L G5l t )a (J lrJ an LJ= ctnl ( R e v. t 2 1 / 0 3 ) t / Y \\ I ffi PERRY NUcLEAR PoWER PLANT Loss of 100'F Feedwater Heating, Automati-c FJow Control F j - g u r e 1 5. 1 - 1
LrJ z (rl f\\l (J lU an lrl- = E IL (s3rHu J0 lN33u3dl x CE tu L (\\f a e(\\l c) Lu tn tll-r F U' lrl-uz v,td TJ z f lrJ lrj E =? L Lr.l gt I TL ttJ E I ts.4, euJ Jttl lrJ > c lrJ J 3 <nl ( R e v. L 2 1 / 0 3 ) iffiil\\ PERRY NUCLEAR POWER PLANT I \\-Yl I Loss of 100oF Feedwater Heating, Manual Flow Control F i g u r e 1 5. 1 - 2
ul r. H iE v\\ F > =H l-lrj H6 o d - L ot) >cr -nl (J l4J afl E F . a C t d I (r r slil$rodt{o] u Il ll]tfro ( R e v. 7 2 l - l 0 3 ) ^6a 1fffi\\ PERRY NUCLEAR POWER PLANT Feedwater Controll-er Failuret Maximum Demand, With HWL TriPs F i g u r e 1 5. 1 - 3 b Gfr d.u, I E tL-G tf, lr, tr.t ]n 14, (\\I tu tlJ (Juf I 8d to3ruu.$ rElu3d) r.i (JU g
1.,- F F =H f-t^r E6 odFb - 6
- !x E';
trJ lrJ J > -l1l TJul I t-gn ( R e v. 1 2 1 / 0 3 ) &NH\\ PERRY NUCLEAR POWER PLANT ...l'l.q u Pressure Regulator Failure Open to 1308 F i g u r e 1 5. L - 4
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E - u J - t - F r U l + t t ti, < - c D I E t - = z = ; X F<fr - j n = Goo ( Rev. t 2 1/ 03) 1f,ilS\\ PERRY NUCLEAR POWER PLANT Hiqh Thermal Power Scram Setpoint for Plant OPeration up to 100t NBR Power F i g u r e 1 5. 1 - 5 MAXfMUM LIMIT = 114%
I t I tl I I I I I r---------'! l l I r ! t r l r l -\\ssd fuss Rlse(p) ....-.. Sddy\\H\\rFo^, ---FElief\\A\\Fb', --.-.q/FUfinon tto Es Eo l!u* oo lo u, 3'0 tl! !10 co t! t0 eo fio nreFed Iirn (soC Ttselsed i;, coc oCLE oC' E oaloc -.tFd{in{rn$SERscD --....\\tssdSsnFor
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2t t0 {.0 llo r! ?! lo to lqo 0O 1,0 2,0 t! .1, ll0 60 7A a0 9Il loJl (Rev. L2 1/03 ) CffiJR) PERRY NUCLEAR POWER PLANT {rig:rl Pressure Regulator Downscal-e Failure Figure 15.2-1,
,o- {J trJ tn I ci I ( 3 i sl!,I:Nciiim ul,1 :r:u3u ur_ IJU dd rn:lbu i0,:,N::H=dl ( R e v. 1 2 L / 0 3 ) rD{ l Cfr*'ry1 PERRY NUCLEAR POWER PLANT Generator Load Rejection Trip Scram, Bypass On Figure 15.2-2 (c E I(L 't I I,L (t I -vr ,-{t{ > u': trJl! J > E=:
t t---a-. 1 trr t'rr.t- _ i-'r' r-r sr.\\\\ "t- ,._._.s-. -\\bssd tussFtse(pE') --.....Sddv\\HrRor
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-..-.q1ps\\6Foil , _ i - _ - t r I t I I I,. I I I It I \\ I I I tto IE&,* n0 t0 nra(ed 3ll nns(sd 79 10 TneFeq ir' x c3 E0ctEo(, b u l!od. Ito t!e,s .16'0+- oo LO nno(seQ rron ffi PERRY NUCLEAR POWER PLANT L \\)<1 Generator Load Rejection Trip Scram, BYPass - Off F i g u r e 1 5. 2 - 3 --..... \\EssdSesnF*ril
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l.!l a L > > t I ) f f. =, EF o0- -o- > c (o_ U 3 a { 5 r s.LN:}rfin,3l drli II I !;i r-l x b x (J !q1 trJz ( R e v. L z r / f i ) .?ar-\\ tr"Jb PERRY NUcLEAR POWER PLANT w Turbine Trip, Trip Scram, H l r t l - : a C
- n. i l - ? I - ' l f ! n F i g u r e 1 5. 2 - 4
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-,f g) 5 g t o o IE oog.: (t a! oc, !{, IE E 3! 1t Trne$eql 3.0 {3 line(seC l! .1.0 nrafta$ a0 .m Tire(secl 1fffi\\ PERRY NUCLEAR POWER PLANT Turbine Trip, TriP Scram' Bypass
- Off, RPT On F i g u r e 1 5. 2 - 5
( R e v. 1 2 1 / 0 3 )
(E E I (L lr, V' I IL raJ I F E = uJ J > Z G r03rw J0 rfl!38=d, (lt-LItrlg t ( R e v. L Z I / 0 3 ) r / x \\ I (ffiM PERRY NUCLEAR POWER PLANT Three Second Closure of a}l Main Steam Line Isolation Valves With Position Switch Scram Trip F i g u r e 1 5. 2 - 6 a
'=*...\\ t..*-- \\.-t'... '\\ '\\-n r \\'* -\\rs-'r"'--*- \\ \\"r- \\ \\'-t-s-. \\ 0 0 1 ! 2 J J t o ( ! l o a o t o a ! -\\tssdRessRbe(tr0 ..-.... Sddy\\AFb^,
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--.-. q1ps\\A\\'eHo/v .ltaf"t"t'*-..a a 1._ j t o! t! 2t t0 .3 5J lo ?! a! J} I a co CLE o(, t ioE !e t! E:s oo 1.0 to 10 5! Tine(se{ 6! tt t! ( R e v. L 2 1 / 0 3 ) l / x \\ I tr'ffi PERRY NUCLEAR PoWER PLANT V Response to MSIV Cl-osure With FLux Scram F i g u r e 1 5. 2 - 6 b 0, tO 29 10 ilo S.0 GO
^( H L A ) - o-an llJE (ncc. rtU1 td (r, cc (f) (L;* )
- 3Ef, J
LL = G trJ N 3E]-) t! trJ lriz J H tr,J a(r)= trJ F >(r) d (\\l c,m - (J l! a u,J = d F N E, A U ' HUJUJ
- t:r=
O)(J(J t z z C - H H l d - f ' J J I lrllrl l L > > t! UJ lrJ E J J I 3t) J 3 l L o J E u - c Jrtr-l F l cEl tl.JI
- l r!l TL-trJ F
l! Fz X L J = L ' ccE = z N(n TU ldJ cf, lrJ L N zo(L F. 3 lJ.,z, ctct ( R e v. 1 2 a a c f c ) ( D = r031uH JF tN3lUSd) o lt) 1/ 03 ) c) (r) - Q LIJ an trl E d F N 8B (03luu J0 rN3lu3dr -,on ffib PERRY NUcLEAR PoWER PLANT Loss of Condenser lfacuum at z Inches Per Second Figure tS.Z-j
q q-l! fl cc (n LrJ z J = Fln m (n L IJJ ql ctr a
- Jtr, av)
UJ N -E] J lJ- = CE trt F N 3o J l! td an o-t!E ct(\\l E A xlrl =- g)c) a z ld-(')J I t c lL> lul! C J I (tr 3(\\ l! l^J d (3 N ( R e v. 1 2 de 1/ 03 ) Los s PERRY NUCLEAR POWER PLANT of Auxiliary Power Transformer Figure 15,2-B N = ct TL UJ EE (J z = lD Lr-
l n - L. \\ ^(11 F{ o-g1 v o-vlll o U J E (/'l cc E. n tJJ A E, u, z. J = tt7 cv J t]-, aau.J - N N v = 3 E ) E J J J U - tLTL = l.tJlrJ CE uJ F o (f) ^ (J UJ U, trJ= ct N O (f, - (J ulan lrJ= d F N 89 (03ruH J0 JN33U3dl c, E' f\\J ( R e v. Affi$b PERRY NUCLEAR POWER PLANT \\JOU Loss of AII Grid Connections F i g u r e 1 5. 2 - 9 UI UJ c)z J lrj G,6 HUJ x 3 (rl(J t z 0 - H lrru (rrJ I lrJ lL> lrJUl G J I cc E
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(\\l IrJ lrj BB (031UU J0 lN33utdr d ct r/03) td B "i ctlrJ L(\\
vr o-r.u vr cc q-E UI L UJ (n G an q-N = o J t L CO = N (J ct(tr l! El ITJ J (rl (rr= IrJ F > ( ' l o o a g l ro3luu J0 lil3ltfSdl . a tn yl F T R e v. L 2 1 / 0 3 ) rD{ )
- ffi PERRY NUCLEAR POWER PLANT Loss of AIl Feedwater Fl-ow F i g u r e 1 5. 2 - 1 0
o**a i** u J ItI tt2. .o (tl I,l N0 .tl {o (J 1I .3. q, hroo It d zE (1
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= f t J --'s o 'n o g o2 l\\, 1t Il-v, c v, o2 11Iral i! B P r ? fir 15 E V V - l l a n s Y. F l a, + H C - s H
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! o H o < > F r H d r r r t ' . l r ' ' ? H P - l r-g! P o g .l . ?e u' *9; A " 68 f E i i r D e u, t D O 3 l l a a O t, F O U I l S l O O V 4 a O o X O r 4 a Z E l ' o t F i F O ! r = F t = O & m r E r.E t tD !t tl F a li o i L C O O .. F C o , u c c F = t ! .t' I c >tlu o gt F {l t l f a n l - t ' l ., r 4 c c l ' < r J F r i ' o O I t 9 l
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l l ? c - t l l t I e l,. A - - t ) - t Z i n e o t ' r a [ ( < r r t H e 6 H h F A o t l - r l 6 a O F rrrQ Cl 116 O A U .<tr Vl a O rytO d f g o t r F v 3 l4j' --f; I ?. t
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t t, G r,, f o t E ' \\ 4 l? t F v O t s < t O F O A lrt C F. e
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- n FeEfrfi H r'fi a
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= . A O O D 33Hgi EFE sg z rE { urEE tr$i +k - m rB -{vlEF lf;Fi +k - m z A r O3el TEE E"E 2, =B { r,EE th$i +k ttl gIEg* 3n m g h i E r { Y 3oail l t l = Z F i { o >T
- 3 F l n
> !-o FT nn 5 no D Z < t r > 1+l
L. ltl = m = - rr n Zo -l b ('lc) T'!3. .ot ulul l\\)o TI t-lo oo tt UJ UJ Oo .T1 7o TA g lr't oo < r r
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a -l tn Y t r t a n f P < c O C = i3PE5 -sgfi3s r z t l H= 2 C
- *ts 7
I 9s' = D O F Z E =* 9o l't "r l,r tt Ifs otr !t t- - : E - l n ! 4 9
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oo EF wwoc .Tt 0 F{ro 3 NJ ut c .n n TNs .o N N N (tl -u m nn d< R= Z t - $P =m _v> fi" 2T
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CONTAINMENT I / X \\ I (tr"*"'b PERRY NUCLEAR POWER PLANT l\\s--4.{ \\ryJ RHR Loop C F i g u r e t 5. 2 - I 4 ( S h e e t L o f 2 )
S/R VALVE CONTAINMENT REACTOF VESSEL ,-rOrr &ffi PERRY NUcLEAR PowER PLANT x-- LPCS F i g u r e l - 5. 2 - 1 4 ( S h e e t 2 o f 2 )
GLOBE VALVE EMERGENCY SERVICE WATER TO DISCHARGE TUNNEL E M E R G E N C Y S E R V I C E WATER SYSTEM HEAT EXCHANGER ( R e v. t 2 1 / 0 3 ) r-:Or^. df'il$b PERRY NUcLEAR PowER PLANr --\\-/- RHR LooP B (SuPPression PooI Cooling Mode) F i g u r e 1 5. 2 - 1 5 ( S h e e t 1 o f 2 1
GLOBE VALVE EMERGENCY SERVICE WATER TO DISCHARGE TUNNEL E M E R G E N C Y S E R V I C E W A T E R S Y S T E M HEAT EXCHANGER ( R e v. 1 2 1 / 0 3 ) trffi PERRY NUCLEAR POWER PLANT RHR Loop A (Suppression PooI Cooling Mode) F i g u r e 1 5. 2 - 1 5 ( S h e e t 2 o f 2 l
uJ u, o u, GJ C) (J.l 3UnlVUSdht:ll'lood Notss3uddns (Rev. 1,2 L/03]r 1 1 ' & \\ l C[i*}) PERRY NUCLEAR POWER PLANT S M Suppression PooI Temperature During Alternate Shutdown (at 3729 Mwt) F i g u r e L 5. 2 - I 1
t* u., c) o-o- (/l
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SE l'o (J TJa I r.J E H F (9 O (\\l o-. a T'rJ d. ' r Z. - ) L lrJ O H J - &. f a rJ 6: TI L) Kg g lJl g8 -i 910 luruvuldt'llr ,-'an 1fffi\\ PERRY NUcLEAR PowER PLANT Suppression Pool TemPerature During Al-ternate Shutdown (at 3833 MWt) Figure 15.2'3'7 a t 2
- r. / 03)
.\\ = o J ECE trJ N N 3o FS = EI tL lr.l E BB d c ; c t ; ' (03luH JII lN33U3d) J lrJ lrJ tc= t\\I 88 (03rUU J0 lN33!L:ldl ( R e v. 1 2 l / 0 3 l, r 1_2S-\\ I Ctr,-;il5 PERRY NUCLEAR POWER PLANT N H L\\><l J Trip of One Recirculation Pump Motor F i g u r e 1 5. 3 - 1
N = E, J u E tu F
- \\t
(\\ 3 J -(n-Ho-g) g)- C L ult! UJ- (ri ('rctr H tf t tt-l lrJ u) CO lf UJ E, arj !.J
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O F [n (o tr,z J E r,t': r^,1 lr,an (n trJ o (Yl ^ (J
- trlv, IJ.J=
ct (\\l UJ= o ' N ( R e v. 1 2 L / 0 3 ) r 1 x \\ l CK*""b PERRY NUCLEAR POWER PL^ANT Trip of Both Recirculation Pump Motors F i g u r e 1 5. 3 - 2 FU 3 F J lr UJ E --:tt F?fJ u l )< . J t-r FG
- can Io-
! l l rri t l! LrJ G I vlI r I ELJz. .J KJ r! J
E - J l i atl L l{ 3 J = tlJa H J tn C\\J C4 (L L!ut (E UI IJ CO ( i UJ lrJ= o N an IJ (Jz. ctr gt Y = (/:t L) t z o-E lrJ ' ar, J r u J tL> trJ UJ E.J I H'E Jg) ll.l > G l!I J = 6 H ,irr* Jo r*J3u3d) CE lrJ= lrJ L' G (03lHU J0 JN33U3dl (E l!' L. a\\l ( R e v, 1 2 t / 0 3 ' ) r h \\ ffiM PERRY NUcLEAR PoWER PLANT \\J5/J Fast CJosure of One Main Recircui-ation Valve at 609 Per Second F i g u r e 1 5. 3 - 3
L('t - g l!, lltl trJr c H(f, tt, I UJ tfri Err]l an o-(!,an ctr U' l!(ft(n i! trJz = ts lr,
- E
. F oN ct ct c o : ' (03luu Jn rNSlu3dr ct ct d L 2 L / 0 3 ) f /)a\\ \\ ffi PERRY NUcLEAR PoWER PLANT Fast Closure of Both Main Recirculation VaJves at llt Per Second F i g u r e 1 5. 3 - 4 fEatlltl LJt^l E = - fi (J L) t z z I tul! t L > >. TLJ UJ IJ f t J J I L)u,J (tl lrj-dF c\\l gB ro3tuu $ lN3JU3d) ct lr, ( R e v. CE ltJ lrJ LJ CE
ctl (L t ! an e (n N ef J l!- IJJ F .\\ = e) Vl,- L(', - q - trj (/)trl - ur, G H G lrJ trJ
- lnz, i! Ol c) 1-tr@
o f1 - (J ut ttl lrj= o(\\ c t !z LrJ -l u'l ('rrE UJF >l.rl anH (Jz G.n Ell.l E = tlrl)t z. o r H U J J @ J I lr, t L > lrJ UJ G J I tu= . l - ct N (J trJ v1 l*J= l-ct(rl ( R e v. L 2 1 / 0 3 ) Cffiil5 PERRY NUCLEAR POWER PLANT Seizure of One Recirculation Pump F. i g u r e 1 5. 3 - 5 FCE lrj I U
- 2, J'.'1 t ' :
> ci lrjJ 3 lu a r l E z
atl0-lrjul Ctr ln UJz J= v1 N e, lrl G f\\l c-tn I l^J N a n - tl-z uJet I a l ! -
- E H u,J u.JL)Ir
(\\l dB (03luu J0 lmJu3dl ( R e v, L 2 1 / 0 3 ) lfn$\\ PERRY NUcLEAR PowER PLANT t v / l-- Abnormal StartuP of Idl-e Recirculation LooP PumP F i g u r e 1 5. 4 - 1
l.! N - vta Nd crcE JlrJ Lts x F-H& (/t 8-s l/l trJ b{es F G .rl/1 E E R a C3 I I E F 5 ct) u lI. t! trt ut H la hF l!=v r E l - 3 v)F nlart dT: 5-z CJH H ( R e v. 1 2 t / 0 3 ) r D d l ff;ffi PERRY NUcLEAR POWER PLANT tD<1 ) v Fast Opening of One Main Recj-rculation LooP Valve at 30t Per Second Figure 75.4-2
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F ( L l r j N N I (/lluJt-i-E' Fl/rl J CtrHl-.NtL I UI c r tl l!u d8 B-(JU H R Etr CEuu EE w39 co f,cc F - = I n F H 9 3 a9 tGlrH J rErHSdl ( R e v. 1. 2 L / 0 3 t, -'an PERRY NUCLEAR POWER PLANT Fast Opening of Both Main Recirculation Loop Valves at 11t Per Second F i q u r e 1 5. 4 - 3
6 ?t Fl ljf F (tr F{ atl ttl lr Or r a d c l c { ? l C { N $ l $ f ( Y co to { t 1 {t rt ct d d a { o ?l tt o tf .-a ltt cD tO tO $l lfl (ll (ll rO { Gt lO l*l Ct ?a G{ ltl Ct tg lO F{ Gl c' a a a a a a a a a a a a " " " t " ' (D Ot tt F old Ol CtNatt :r ? F r'{rn Gl +{ C{ C{ tfl A 4 tl Ol o ct dt i iri b - c-i,i i r-or ui t'f c{ rl trr 6 co (l dr N M o - m to o I Ft rnr ; 6 an o F Fi cD -r N ro cr (Y ?'l N (-Q l! I ro F F i grr-cr o ico iri o b -{ q! !! c{ N trt q g! 9! ql ts k sr si or cr cr Ft N ct t't t f cl l' rt Gl ct ct fo ct f" (rl Gf rl lrl Ut f-ol c{ e lt) ro It (\\= fn !t F' o frl lo c. ol c{ F{ { Fl o Fa ra r? d O t ! 7 F a c, t t Fl f\\(\\, t l ' l s r o H F I H?E $l d - & 4 F l o & N (^, q HtrI CN h H F. 7 H O - t \\ ( J F { t O l{ ,..t 03! ?< C ? J H r l d o A o
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,( trl r < E x o t(o. ( R e v. t 2 t/03) trffi PERRY NUcLEAR POWER PLANT _ v _ Critical Rod Pattern for Misplaced Bundle Accident F i g u r e 1 5. 4 - 4
1. SCENARIO I EVALUATION COiDENSER
- 2. scEl{ARro 2 EVAUTAnON COT{DENSER E N V I R O N M E N T OFFGAS TREATMENT SYSTETII ENVIRONMENT (Rev, t z 1 / 0 3 )
&fib PERRY NUcLEAR PowER PI-ANT \\].ATJ -\\/- Leakage Path Model for Rod DroP Accident F i g u r e 1 5. 4 - 5 DECAY OF NOBI.E CIASES A10 ffiTElmON oF lolrll.lE
PIJ}TT COORDIt{ATE 47 ---l { 3-39 35 31 23 l9 15-I I ll -F I I I 2 610 I 50 54 58 lil rr--+--i----!-- ri! '---+---f:i 5, --j- --l l 4 II I t8 I 22 26 I 46 I I 27 il! -!-u--L--- iil l--i--i-- lil ( R e v. L 2 1 / 0 3 ) trffi PERRY NUCLEAR POWER PLANT N--6 -'H Rod Pattern for RWE Analysis 14 Core Geometry (Rated Power Case) F i g u r e 1 5. 4 - 6 7 ---f---j-- II --{---- I --J--- I I I ffi-l--l-3 -r-*---r IIi I
tr, r,LN'E tna)E lrJ(L f > -F-J (03lUH JCI 1f,l33U3dl vr trJ-- otd 2 roflHu s ll{3tu:ld) llev. 12 1/03) t 1 ^ \\ I ffiM PERRY NUCLEAR POWER PLANT \\-JQ(r Inadvertent Startup of HPCS F i g u r e 1 5. 5 - 1
UJ g o Fv7 UJ = co CE l-.- IJJ' IJJ z > ei 5 > F ZI v, I Eo 22 c o osi F ! o ilJ \\j tJJ 4 Ut o I o E G Gul 3o UJ uJ tl. tt) IIJ UJ z > < 7 u,l = F Y ( ^ F z < ( 9 > 0 J IJJz , 2
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F \\.- E \\ r.! \\tr\\ t n-\\ \\_J LlJ J E P v ( ) ( J G ; b6 UJ E 3 tJ-3 l.l-UJ v)
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uJtr Fz IJJ== zo ( R e v. t Z 1 / 0 3 ) /-lOn dffi*\\ PERRY NUCLEAR POWER PLANT w Steam Flow SchemaEic For Steam Break OuEside Containment' F i g u r e 1 5, 5 - 1
U-T r-tr:(D <O UO -T t-t-tr ^. { ' - ( D = .l-o =at-N) .ro a 1-(, (n 1-(, cFo m l -\\ o l 3 0 l d U -T t-tr: CI rnc )) H - n)-\\ qor J L f f c u (Dc - l cl- <-l _o ctr LE 1la a(n (n !.\\ 0f t-tr (D o_ C l(, c-l A) I-tr 0o_ a -O -I Ol r-troo_ 1-fo C) a !.T OJ II 0o_ C l a !-I 0, r-C (D o_ cfo f fc tra a T.J 0l r-troo_ c+o D) ltr tra >rn C) -t a J ltr ca m J P-I o l 3(D l 4-f C-) o l .l'-I Too3 ? 2 {-t OJ; lao_5 jJ qT 7lgL )r =o O CF lr . F l'
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^-x ax r_o ; (D\\ T5 qL +(D J, OJ IIa ma l l l = 0 ' .i o* lo-J( D + l o cF a r-tr 1l 0f ag C J(, !-I 0, r-tr CIo_ clo a T-I 0r r-tr 0o-U .T Ltr E 0 FJ cl-o C){, !-I 0l TE (D o_ do at-cl-o m f -\\ o l 3 CI l cl. < O g1 -l 1-1tr 0 TN aTl t-(D a T Ol rO 0 c-) T l 1-l-0f To C) T m X Totra d 3m -o N t\\) N g Tm Tn d-< Rz. Z t - qc) ,39 fi" 2n
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FLOW.-+ CO NT A I NME NT Cfffi\\ PERRY NUCLEAR POWER PLANT v Leakage Path for Feedwater Line Break Outside Containment F i g u r e 1 5. 6 - 3
r--- I I I I NUCLEAR SAFETY OPEFIA'IONAL CRITEFIA NUCLEAF SAFETY O E S I G N C R I T E R I A ANTICIPAT O OPFATIONAL TRANSI NTS 8WR OPERATIN STATES IOENTIFICATION OF SAFC,TY ACTIONS REEULTS (EACH STATE} FULES FOR EVENT ANALYSIS IOENTIFICATION OF SYSTEMS ANO LIMITS ESSENTIAL FOR ACHIEVING SAFETY ACTIONS IEACH STATEI IOENTIFICATION OF INTRASYSTEM ACTIONS WFIICH MUST 8E FEOUIRO OR RFSTFICTEO IEACH EYSTEMI IOENTIFICAYION OF MINIMUM SYSTEM HAFDWAFIE CONOI'IONS TO ACCOMPLISH ACTIONS IEACH SYSTEMI TOENTI FICATION OF HAROWARE CONDITIONS 'O SATISFY fIEOUNOANCY REQUIREMENTS ACH SYSTEM (OPEBATIONAL NUCLEAR S ^ F E T Y F E O U I R E M E N T S, L I M I T I N G CONOITIONS FOR OPERATION} I O E N T I F Y S U R V E I L L A N C E TEST FFEOUENCIES A V A I L A E I L I T Y CONS IDE RATIONS I O E N T I F Y A L L O W A B L E F E P A I R T I M S WHEN SYSTEM TNOPEFAELE ILIMIlING CONOIIION FOR OPERATION} SYSTM.LEVEL OUALITATIVE PLANT DESIGN BASIS C O N F I R M A T I O N SYS'EM.LEVE L OUALITAIIVE SYSTEM DESIGN EASIS C O N F I R M A T I O N S Y S T E M. L V E L OUAL ITATIV E P L A N T S A F E T V I ^*o^, toi-. t^---;l I orenarrornr-REoutRE' I
- M E N T S N o r s a r t s F t E D L r - r + - - d SIMPLIFICATION
( R e v. 1 2 1 / 0 3 ) PERRY NUCLEAR POWER PLANT Block Diagram Used to Derive Nuclear Safety Operational Requirement, System Level QuaLitative Design Basi-s Confirmation Audits and Technica] Specifications Figure l-5A.2-1
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==eH EE[5 - f t - u J 9 o o > hHrs ) uJ UJ J zo FU I.IJ J F U J o o > E IEUJ zo F(J U J J F r.u o o > z E u z 9 F() L U J F U.l o > E W h U) -: l- {i, Efi k= E O EH z O F C) t! F C I o UJ J zotr O UJ Fo r F = zis =l.U Eq sd c lll otr oz z F u t J F u J p o ) LD CC lrr e O - J ( R e v. 1 2 1 / 0 3 ) ,FHE* < r - r l u a t r E<Eftr tr3:5P E3H:E IEagtt HE3!3 Eeiiis ifiElEi uJz (L d', z o o v t !{ fru1 r t - Z O o u l HHi Iils Fil3 r U ) Z 26t t r p o l r D t r u EHi-z5E g o b LHT F UJ llJ n' = E V) uJ q) Fz UJ UJ Fzt! 2 7 f, ; - -l 1-u.r i u, -) 65 z < 6 > tr F tu o-LIJ lY
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6;3= i l oEH zo F(J IJJ F E t o-uJ I > F r,! l I ) J 2o F uJ r' c c J L U J I > F t ! r f, J zo F L) UJ F-o r ! J o-1g o > E u l ( f ) J z F t! F EL g1 o > z u c\\t J J F1fr AE k= t ro EH zo F r.lJ F F I
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' o \\ Fz uJ uJ Po PERRY NUCLEAR POWER PLANT s s i b L e I n c o n s i s t e n c i e s i n E h e S e l e c t i o n o f N u c l e a r S a f e L y Operat ional Requirem.ents F i g u r e 1 - 5 A. 2 - 2
EVENT EVENT TITLE STATES i9, NUMBER OF EVENT STATES IN WHICH THIS PROTECT]ON SEOUENCE IS APPLICABLE D] FFEHENT PLANT CONDITION PERSONNEL (MANUALI ACTION REOUIRED FOR SYSTEM W SYSTEM MUST ITSELF MEET THE SINGLE FAILURE CRITERION INDICATES THAT ONE OR MORE OF THE KEY PROCESS PARAMETERS MUST BE LIMITED TO SATISFY NUCLEAR SAFETY OPERATIONAL CRITER IA EACH CONNECTED PROTECTION SEOUENCE IS FOR JUST ONE SAFETY ACTION DI FFERENT PLAN CONDITION INDICATES THAT SYSTEMS O AND F SHARE AS A PAIR THE REOUIREMENT TO MEET THE SlNGLE FAILURE CRITERION ( R e v. 1 2 I / 0 3 ] ' ffiffi PERRY NUcLEAR PoWER PLANT M r{X Format for Protection Sequence Diagrams F i g u r e L 5 A. 4 - 1
FRONT LINE SAFETY SYSTEM x SAFETY SYSTEM AUXILIAHY A SAFETY SYSTEM AUXILIARY B SAFETY SYSTEM AUXILIARY C DIAGRAM INDICATES THAT AUXILIARIES A,8. AND C ARE ESSENTIAL TO THE OPERATION OF THE FRONT LINE SAFETY SYSTEM X. NO CHRONOLOGY OR ORDEB OF ACTION IS IMPLIED PERRY NUCLEAR POWER PLANT Format for Safety System Auxiliary Diagrams F i g u r e 1 5 A. 4 - 2
2 u t ' ! ! u JsiIi ^ F t t l r = ? l L g,ri*E r5{d i r r ! = E nEu ' " = = iaEi i= 9! HqHi a6hH = = dF ( R e v. t 2 1 / 0 3 ) Cflffi\\ PERRY NUCLEAR POWER PLANT wo Format for CommonalitY of Auxiliary Diagrams Figure l-5A. 4 -3 Io S = J t ! = F = ( 4 4 > q g t l > F u.l IJJ F rL (n ( 4 l ( o r r, t r a x , = B 9".=.t: u J f, > : ) UJ b < t,. r
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( R e v. L/ 03) L2 E ; i!i: Irr H!g ffiM PERRY NUcLEAR PoWER PLANT l\\lrF#t X..P Safety System AuxiLiaries F i g u r e 1 5 A. 5 - 1
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&ffi PERRY NUCLEAR POWER PLANT \\ \\-x-l --/- SafetY Action Seguences for Normal OPeration in State D' F i g u r e 1 5 A. 6 - 6
{.-EY,F,ryTr-^-\\ M A N U A L O R INADVERTENT SCRAM REACTOR PROTECTION SYSTEM S I F CONTROL ROD DRIVE SYSTEM s l F SCRAM nan trffi PERRY NUcLEAR PowER PLANT ._r(X Protection Sequence for Manual or Inadvertent Scram Figure 15A.6-7
S T A T E S A, B STATES C, D PLANNED O P E R A T I O N S C R A M S I G N A L W H E N 3 M A I N STEAM LINES C L O S E D > 1 0 % I N S E R T C O N T R O L ROOS HIGH PRESSURE LIFTS VALVE T R A N S F E R R I N G HEAT TO SUP. PRESSION POOL S T A R T H P C S, R C I C, O N W A T E R L E V E L 2 ( R e v. 1 2 1 / 0 3 ) Protect.ive Sequence for Loss of PIant Instrument or Service Air SYstem F i g u r e 1 5 A. 6 - 8 S E R V I C E A t F SYSTEM STATES REACTOF PROTECTION SYSTEM PF ESSU R E R E L I E F SYSTEM CONTROL ROO D R I V E S Y S T E M I N C I D E N T DETECTION CIRCUITRY P R E S S U R E R E L I E F MAINTAIN l,vATER LEVEL CORE COOLING ,ffi) PERRY NUcLEAR PowER PLANT tts#T
EVENT 9 INADVERTENT START.UP HPCS PUMP STATES A, 8. C AND D FEEDWATER CONTROLLER PRESSURE REGULATOR FAILURE FAILUFE STATES B, D SEE EVENT NO.23 PLANNED OPERATION STATES A r C STATES B, D PLANNED OPERATION MAXIMUM DEMAND PLANNED OPERATION SEE EVENT N O. 2 2 ( R e v. 1 2 1 / 0 3 ) (ffi pERRy NUSLEAR pOwER PLANT l \\-v/ l Protective Sequence for Inadvertent Startup of HPCS PumPs F i g u r e 1 5 A. 6 - 9
EVENT IO STARTUP OF IDLE RECIRCULATION PUMPS STATES A, B. C, D \\ j STATES B AND D STATES A AND B POWER l0-60% STATE POWER ee 3 tr UJ3o cV EQ lo IRM H I G H FLUX SIGNAL rr oton tr, llj3o G \\PRM { I G H
- LUX
- IGNAL NE MC SY UTRON
)NITORING STEM NEUTRON MONITORING SYSTEM rLANl\\trU TL'T OPERATION OPE s l F F REACTOB PROTECTION SYSTEM SCRAM SIGNAL ON NEUTBON MONITORING SYSTEM TFIP S T F CONTROL ROD DRIVE SYSTEM INSEFT CONTROL RODS s f F / \\ SCRAM \\ / (Rev. LZ l-l03 ) D 5.10% RATION r D f l I .fl-'-'M PERRY NUCLEAR POWER PLANT Protective Sequence for Inadvertent Startup of ldle Recirculation Loop PumP F i g u r e 1 5 A. 6 - 1 0
RECIRCULATION LOOP FLOW CONTROL FAILURE MAXIMUM DEMAND STATES C AND D NEUTRON MONITORING SYSTEM REACTOR PROTECTION SYSTEM CONTROL ROD DRIVE SYSTEM STATE D, MODE SWITCH IN RUN, POWER OPEHATION HIGH NEUTRON FLUX (APFM} SIGNAL TO RPS SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL FODS STATE C STATE D (MODE SWITCH NOT IN RUN} PLANNED OPERATlON ( R e v. 1 2 1 / 0 3 ) t /-L\\ l CffiM PERRY NUCLEAR POWER PLANT Protective Sequence for Recirculation Loop Flow Contro] Failure Maximum Demand Figure 15A. 6-l-1
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E V E N T I 3 RECIRCULATION LOOP PUMP TRIP ON OR EOTH STATES C ANO D ONE PUMP TRIP PRESSURE RE LI E F SYSTEM CONTAINMENT ANO REACTOR VESSEL ISOLATION CONTROL SYSTEM REACTOR PROTECTION SYSTEM INCIDENT DETCTION CIFCUITRY MAIN STEAM LINE ISOLATlON VALVES CONTROL ROD DRIVE SYSTEM MAINTAIN WATER LEVEL REACTOR VESSE L ISOLATION STATE C ONE PUMP TRIP STATE O TWO PUMP TRIP PLANNEO OPERATION O NE P UMP T RI P HEAT TO SUPPRESSION POOL S T A R T H F C S. R C I C, O N W A T E R L E V E L 2 ( R e v. 1 2 1/ 03) { " r \\ l O6"'}D PERRY NUCLEAR POWER PLANT l \\ \\ 1 / Recirculation Loop Pump Trip one or both F i g u r e 1 5 A. 6 - 1 3
E V E N T 1 4 ISOLATION OF ALL MA!N STEAM LINES STATES C, D REACTOR PROTECTION SYSTEM PRESSURE RELI EF SYSTEM PRESSURE R E L I E F CONTROL ROD DRIVE SYSTEM INCIDENT DETECTION CIRCUITRY MATNTAIN WATER LEVEL INITIAL CORE COOLING STATE C STATE D SCRAM SIGNAL WHEN 3 MAIN STEAM LINES CLOSED > 10% HIGH PRESSURE LIFTS VALVE TRANSFERRING HEAT TO SUP. PRESSION POOL START HFCS, RCIC, O N W A T E R L E V E L 2 ( R e v, 1 2 1 / 0 3 ) Cfl*'6 PERRY NUCLEAR POWER PLANT Protective Sequence for fsolation of All Main Steam Lines F i g u r e 1 5 A. 6 - L 4 ( S h e e t 1 o f 2 )
LESS THAN 90% POWER GREATER THAN 90% PowER CONTINUE PLANNED OPERATION HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS ( R e v. 1 2 1 / 0 3 ) (T'""D PERRY NUCLEAR POWER PLANT Protective Sequence for Isolation of One Main Steam Line F i g u r e 1 5 A. 6 - 1 4 ( S h e e t 2 o f 2 l EVENT 14 ISOLATION OF ONE MAIN STEAM LINE STATES C, AND D NEUTBON MONITORING SYSTEM REACTOR PROTECTION SYSTEM CONTROL ROD DRIVE SYSTEM
fvFx? t3 maovtrYe'lt orENrxo of A saFrlY' Rt rlr valva trattt ^. a. c ^xo o io tlaurvltEi RACTON PFOreClrOrl SYSTEM TRANTFF OECAY XCA' 'O sttPRE5Sl0l{ rooL IIAET HrcElFCI A'ID csct uirFcgtcctlv Tnlt SEllrr{c3tlAnT ADt nuro{Atrc FEcolYAlEi tLorv collTnol tt^T 0l FEOt'lnD vllvES TO MArilTAll{ og. PnESSUAlzATlor{ tflrrtaTE scRAM or{ LOWWATEB LEVL INSCFT CONTNOL ROOS t,rtTtar cLoauRE Or LL csat^lfl$ExT lsolAtloil vALVtr ttcE TMAla{tll^l, LtN OiI X16I{ OFYTT'ELL faesEuR AOS AC?Ulreo S.}'TNESEIOI{ '(X,L TEMPERATUi LIM II, START OCFTESSUF IIA'ION -'an df"i$b PERRY NUcLEAR PowER PLANr tryJ Protective Sequences for Inadvertent OPening of a SafetY/ Relief Valve F i g u r e L 5 A. 6 - 1 5 ( R e v. L2 1/ 03 )
EVENT 16 CONTROL ROD WITHDFAWAL ERROR START.UP AND REFUELING OPERATION STATES A AND B NEUTRON MONITORING SYSTEM REACTOR PNOTECTION SYSTEM BEACTOR PROTECTION SYSTEM CONTROL ROD DRIVE SYSTEM CONTROL ROD DBIVE SYSTEM ROD BLOCK PLANNED OPERATION oo G otr l.-zoo ozo (t UJ a tLo o= l!tr 3 tr, o Tl-F ooE tu zo STATE B INTERMEDIATE RANGE ,.REFUEL" HIGH NEUTRON FLUX SIGNAL SCRAM SIGNAL ON NEUTRON MON ITOR ING SYSTEM TRIP ffiM PERRY NUCLEAR POWER PLANT Fra-/,zt Protective Sequence for Control Rod Withdrawal Error for StartuP and Refueling Operations Figure 15A.6-15 ( R e v. L 2 1 / 0 3 )
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EVENT 19 RHRS-SHUTDOWN COOLING INCREASED COOLING STATES A, B, C. AND D PLANNED OPERATION PLANNED OPERATION t / ) < \\ l CffiN\\ PERRY NUCLEAR POWER PLANT RHRS Shutdown Cooling Failure Increased Cooling F i g u r e, 1 5 A. 6 - 1 9
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EVENT 21 LOSS OF A FEEDWATER HEATER STATE D BEACTOR PROTECTION SYSTEM CONTROL R O D D R I V E SYSTEM RECIRCULATION FLOW IN RECIRCULATION FLOW IN AUTO H I G H F L U X SCRAM SIGNAL (THERMAL POWER MONTTOR} SCRAM SIGNAL ON NEUTRON MONITORING SYSTEM TRIP INSERT CONTROL RODS PLANNED OPERATION ( R e v. 1 2 l_/03 ) (ffi pERRy NUcLEAR pOwER pLANT r{ts Protective Sequence for Loss of a Feedwater Heater Figure 15A.6'21
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EEEH E=;gI 5zo o uJ Fo E=o etd $ ? EIE, C' HIfi=H E ffi PERRY NUCLEAR POWER PLANT X-H Protectj,ve Sequences for Pressure Regulator Failure OPen Figure 15A.6-23 1/ 03 ) ( R e v. 1 2
EVENT 24 FIRST PRESIIUFE R EGULATOR FAILURE - CLOSED STATES C AND D SECOND PRESSURE REGULATOH PRIMARY CONTAII.IMENT AND REACTOR VESSEL ISOLATION CONTFOL SYSTEM MAINTAIN CORE COOLING MAIN STEAM LINE ISOLATION VALVES INITIAL CORE COOLING RHRS - supPREsSf ON POOL 'COOLINc i,tODE MANUAL FV OPRATION PLANNED OPERATIOT{ START HPCS, RCIC ON LOW WATEB LEVEL SUPPRESSION POOL TEMPERATURE LIMIT STAFT DEPFESSURIZATION REOUIRED VALVES FOR COITITFOLLED DEP MAINTAIN WATER IN REACTOR VESSEL Tm -o S t\\) N g Tmnn d-< Rz z t -sP =m , " ) fi-2ru
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EVENT 32 INADVERTENT LOADING AND OPERATION - FUEL ASSEMBLY IN IMPROPER POSITION STATES A. B, C, D P L A N N E D OPERATION ffi-M PERRY NUCLEAR POWER PLANT - v Protective Sequence for Inadvertent Loading and Operation of FueI AssemblY in fmproPer Position Figure 15A.6-32
E V E N T 3 3 FECIRCULATION LOOP PUMP S E I Z URE STATE O ONLY PHESSURE R E LI E F SYSTEM I NCI DE NT DETECTION CIRCUITFY I NCI OENT DETECTION CI RCUI T F Y PRESSURE RE LI E F MAIN STEAM LINE ISOLATION VALVE REACTOR PROTECTION SYSTEM CONTROL RO O O RI V E SYSTEM MANUAL RV ACTUATION SNSES HIGH REACTOR VESSEL WATR LEVEL SENSES LOW WATER LE V E L ( R e v. 1 2 1 / 0 3 ) f / ) < \\ I ffi PERRY NUcLEAR POWER PLANT Protective Seguence for Recirculation Loop PumP Seizure Figure 15A.6-33
E V E N T 3 { RECIRCULATION LOOP PUMP SHAFT BREAK STATE D ONLY I NCI DENT OETECTION CIRCUITRY INCIDENT DETECTION CIRCUITBY MAIN STEAM LINE ISOLATION VALVE REACTOR PROTECTION SYSTEM CONTAINMENT ISOLATION SENSES HIGH REACTOF VESSEL WATER LEVEL ( R e v. L 2 1 / 0 3 ) Cffi".$ PERRY NUCLEAR POWER PLANT \\12(l_J Protective Sequence for Recirculation Loop Pump Shaft Break F i g u r e 1 5 A. 6 - 3 4
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EVENT 36 FUEL HANDLING ACCIDENT OUTSIDE CONTAINMENT STATES A, B, C, AND D CONTROL ROOM
- HEATING, VENTIIATING AND AIR CONDITIONING SYSTEM CONTROL ROOM ENVIRONMENTAL CONTROL
-ran /ffi;-h\\ PERRY NUCLEAR POWER PLANT t \\ - ! a / l r-<x Protective Sequences for Fuel Handling Accident Outside Containment F i g u r e 1 5 A. 6 - 3 6
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EVENT {I GASEOUS RADWASTE SYSTEM LEAK OR FAILURE STATES A, B, C, D MANUAL OPERATOR ACTION MAIN CONDENSER LOW VACUUM OFF.GAS SYSTEM ISOLATION STATES A. B STATES C, D PLANNED OPERATION SEE LOSS OF CONDENSER VACUUM EVENT 26 (Rev. 12 1/03 )
- Ifffi, PERRY NUCLEAR POWER PLANT Protective Sequences for Gaseous Radwaste SYstem Leak or Failure Figure 15A' 6-39
STATES A, B STATES C, O PLANNED OPERATION EVENT d2 AUGMENTED OFF-GAS TREATMENT SYSTEM FAI LURE STATES A, B, C, AND D MANUAL OPERATION ACTION MAIN CONDENSER HIGH PRESSURE OFF.GAS SYSTEM ISOLATION SEE OTHER LOSS OF CONDENSER VACUUM EVENT 26 ACTIONS rr'on ffi*'"Y1 PERRY NUCLEAR POWER PLANT \\JclU Protective Sequences Augmented Offgas Treatment System Failure Figure 15A. 6-44 ( R e v. t 2 1 / 0 3 )
/ E V E N r 4 3 \\ / R A D I O A C T I V E L I Q U I D W A S T E \\ S Y 5 T E M F A I L U R E S ( R E L E A S E T O A T M O S P H E R E ) \\ srATEs A, B, c, D -/ H l G H R A D I A T I O N P R O C E S S V E N T I - LATION RAD]ATION M O N I T O R I N G SUBSYSTEM V E N T I L A T I O N SYST EM CONTROL / \\ R E S T R I C T B U I L D I N G ACCESS \\ / ( R e v. 1 / 0 3 ) ffi PERRY NUCLEAR POWER PLANT \\.ry Protect,ive Sequences Augmented Liquid Radwaste System Failures Figure l-5A.6-4L
,/ EVENT 44 \\ / P O S T U L A T E D R A D I O A C T I V E \\ L I Q U I D R E L E A S E S D U E T O LIQUID.CONTAINING TAN K FAI L- \\unes srATEs A, B, c, or/ H I G H W A T E R F L O O R D R A l N M O N I T O R I N G SYSTEM SUMP PUMP SY ST EM / C O N T A I N L I Q U I O E F F L U E N T \\ \\ / (Rev. t / 0 3 ) P PERRY NUCLEAR POWER PLANT rotective Sequence for Liquid Radwaste System Storage Tank Fail-ures Figure 15A. 6-42
EVENT 45 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT STATE A CONTROL ROOM
- HEATING, VENTII.ATING AND AIR CONDITIONING SYSTEM CONTROL ROOM ENVIRONMENTAL CONTROL I
/ ^ \\ Cffi;n) PERRY NUCLEAR POWER PLANT {Tg-t Protecti-ve Sequences for Fuel Handling Accident Inside Containment F i g u r e 1 5 A. 6 - 4 3
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F5 le E + A A ajg lZd Cilffi\\ PERRY NUCLEAR POWER PLANT ...lll..S U t E l I _ v _ Protective Sequences for Reactor Shutdown From Outside Main Control Room Figure 15A.6-45
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[, TIHE 6. rSEC) u, 6. TIl,tE (sECt TET4P FLUX F-5EP-SKI RT VEL I INCHES} ( INCHESI ) r,,t I (PCT ) I NEUTBON 2 PERK F VESSEL 5 UX CENTER r LEVELTINdH-RE 2 t.I R sENSflD LE 3NRSENSSOLE -100. 0. ( R e v. t 2 7 / 0 3 l l CK'*E PERRY NUCLEAR POWER PLANT Generator Load Rejection with Blrpass Failure 3729 MWt Core Power 100* Flow 3?0oF Rated FWT Figure 15D-L (Sheet 1 of 2)
I VEssEL 2 sTH LINE SRFETY V q NELIET V 5 BYPRss V 6 TURB STE RI SE IPSI I 5 RISE IPSII t o) o l Vt FL0l'l (o) FLOI.J IPCTI f) l- -l. F L)cr l'r-, E, {. TII.IE 6. rSEC) I VOIO BE 2 OOPPLER TIvITY IVITY TIVITY 2. TIT4E ISECI I r, ! \\ l 06*"D PERRY NUCLEAR POWER PLANT I t v t l Generator Load Rejection with Bypass Failure 3729 MWt Core Power 100t Flow 370oF Rated FWT Figure 15D-1 (Sheet 2 of 2l ( R e v. t 2 1 / 0 3 )
I NEUTRON 2 PEBK FUE 3 RVE SUBF UX CENTERTEHP RT FLUX LEVEL(INCI.IES) EVEL ( INCI-IES] er uJ Fcr E TL C) Fz, trJ L'cc u.J TL ERH FLol.l I LEVELII F-5EP-5K I BT u. TII'lE 6, (sEC) 2].lR 3NR {. TI},IE 6. rSECl ( R e v. t 2 1 / 0 3 ) Cflffi5 PERRY NUcLEAR PowER PLANT L \\)<,/ ,/ Generator Load Rejection with Blpass Fail-ure 3729 MWt Core Power 100? F.l-ow 320oF Rated FWT Figure 15D-2 (Sheet I of 2\\
u. TI},IE 6. (sEC) I VESsEL 5 nlsE lPSi ) 2 STH LINE 3 SRFETY V 5 RISE IPSI ] FL0l'l (ol [EH-to) VE FL0l'l {o) FLol.l lPcTl VOID RE TIVITY DOPPLER RCT IVITY TIVITY SCRRH RE 9. l-(J CE lrJ GC 2. TIIIE f n)a\\ 'l
- ffi PERRY NUCLEAR POWER PLANT T.FIJ Generator Load Rejection with Bypass Failure 3729 MWt Core Power 100t Flow 320oF Rated FwT Figure 15D-2 (Sheet 2 of 2)
( R e v. t 2 1/ 0s )
Ebl I F rflslrct{Hrm ulAtr$* Itt_ L'!f H -a .F nl L2 r./03) Generator Load Rejection with Bypass Failure 3729 MWt Core Power 1008 Flow 250of Rated FWT Figure 15D-3a dffi PERRY NUCLEAR POWER PLANT I fv-/ I r-rQ(r
I NEUTRO 2 AYE SU 5 CORE I FLUX FACE HEAI FLI LET FLOI{ J i.' lr \\ \\-\\-.^ \\ \\ \\ \\ \\\\ CI TI = loc.. c CI -(, t Ll A 0. c e 0.0 .lr 0 rtilE (sEEoltosl {o0 nilE tstcoilosl t JI t-C' 4-C' a, .J ral J nllt (ttcoltosl .1.0 rillt tsEcoltDst afaaa r-0r0 t.0 ff"*il) PERRY NUCLEAR POWER PLANT Generator Load Rejection with Blpass Faj-lure for Power Uprate 1 0 0 t P o w e r, L 0 5 t F l o w, 2 5 5. s o F F W T Figure 15D-3b I LEYTL( 2 YESSEL 5 TUR8Iil I r E r n u l NCH-nF-seP-: srtAlrFL0t{ sTEllrFL0l{ ? O F I i U IRT ) ft F \\- -.--. v wtl ( R e v. 1 2 1 / 0 3 )
I NEUTRON 2 PERK FUE UX CENTER TEI4P RT UX 10. TIT'IE 15. rsEcr I LEVEL ( IN 2 Ft R 5EN5 H-REF-5EP-5KIBT O LEVEL(INCHES) FL0l.{ t F r rPcT) N R 5EN5D LEVEL I INCHES) NL 5 DRIVE FL
- 15.
20 rSECt ( R e v. 7 2 L / 0 3 l ' f / Y \\ I Cf'ffi PERRY NU.LEAR PowER PLANT Feedwater ControLler Failure 3729 MWt Core Power 100t FJow 37OoF Rated FWT Figure 15D-4 (Sheet 1 of 2) 10. TII.IE
10. TI}IE 15. tSEC] VE55EL 5 RISE IPSI) 5TI"I L I NE 5 RIsE IPSI ) RISE (P5I ) sUB (ETU/LB) VE FLOhI (PCT) FL0H IPCTI VOI TIVITT TIVITY TIVITY I2 F - 1. F L' CE lrJtc 10. TIIIE ISEC) ( R e v, 1 - Z 1 / 0 3 ) ffi$A PERRY NUCLEAR POWER PLANT Feedwater Controller Failure 3729 MWt Core Power 100t FLow 3700F Rated F9{T Figure 15D-4 (Sheet 2 of 2)
TET,lP FLUX UX CENTER E HERT T NEUTBON 2 PERK FUE 3 RVE A loo. lrJ FcE tr-e F= ii r 5n-6Eur L 10. TIT,IE 15. rSEC) I I F-5EP-5KIBT LEVEL I INCHES) VEL ( INCHES) L 5 t LEVE 2l. lR 3NR 15. rSECl t0.TIHE ( R e v. 1 2 I / 0 3 ' ) Ctrffi\\ PERRY NUGLEAR POWER PLANT FTA-4F{ L \\)<1 -/ Feedwater Controll-er Failure 3729 MWt Core Power 100t FIow 320oF Rated FWT Figure 15D-5 (Sheet 1 of 2l
T} l-F Fc) CE t!c VESSEL 5 NISE (PsI} TH LINE PRES RISE IPSI} INE RI SE IPSI ) vE FL0H IPCTI FLoH {PCT)
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15. TIHE ISECI IVITY ERCT IVI TY TIVITY rsEc) ( R e v. 1 2 t/o3l I / ) < \\ I CK"M PERRY NUCLEAR POWER PLANT Feedwater Controll-er Failure 3729 MWt Core Power 1008 Flow 32ooF Rated FwT Figure 15D-5 (Sheet 2 of 2) 10. T I I,IE
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- ffi PERRY NUCLEAR POWER PLANT
- v - Feedwater Controller Fai]ure 3'729 MWt Core Power 100? Fl-ow 250oF Rated FWT Figure 15D-6a (Sheet L of 4)
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^Or\\ .Vffi PERRY NUCLEAR POWER PLANT Feedwater Controller Failure 3"129 Mvilt Core Power 100* FIow 25ooF Rated FWT Figure 15D-6a (Sheet 2 of 4) J TL IU l-f G(f LJn
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F H > - >- > t-- l-r-t r-t ts 1.,-> ) L) r-r F { C f F F t J., ( J l, J F E CI E(J(n fr lrJ n-o_ n a Cf, (v cr F19 F a LN Fl F(J UJ (n _. uJ r J = -J l-{ F-rran ff-"6 PERRY NUCLEAR POWER PLANT Feedwater Controlfer Failure 3729 MWt Core Power L00t F.l-ow 250oF Rated FWT Figure 15D-6a (Sheet 4 of 4) (Rev. 1,2 I/ 03)
I rEr 2 8tF T NEL { 8TP EL PRE88 RI TY VALYE FI. IF VALYE T[ s\\ALYE rr I iE(PS t I It It lla , -) lc.a tIlE (sEc0x08l ulc (sEc0llogl .a tt,g o.l C' G-C' a, a, trlt- -l.f lc.a ilffi (5EC0l08l 1fffi\\ PERRY NUCLEAR POWER PLANT r-<x Feedwater Controller Failure for Power Uprate f00t Power, 1 0 5 8 F l o w, 2 5 5. 5 o F F W T Figure 15D-6b ( R e v. 1 2 7 / 0 3 )
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NEUTRON PERK FU 6. rSEC) I LEVELII F-SEP.SKINT 2r.rR LEVEL ( INCHES I N N L I INCHESI TTTEH-(PCTI hr I lPcTl q. TI}tE ISEC I ( R e v. 1 2 1. / 0 3 ' ) ^,o^ C(ffi\\ PERRY NUCLEAR POWER PLANT t \\ Y /, v - Generator Load Rejection w/A Blpass 3729 MWt Core Power L05t Core Flow F i g u r e 1 5 E. 3 - L ( S h e e t I o f 2 )
nlSE (P5t I R I S E ( P 5 I I 0l.l (ol q. TIHE 6. tsEct F L)cr lrJcc ISECl ( Rev. 1, 2 1 / 0 3 ) (ffiM PERRY NUCLEAR POWER PLANT Generator Load Rejection w/O Bypass 3729 MWt Core Power 1O5t Core Flow F i g u r e 1 5 8. 3 - 1 ( S h e e t 2 o f 2 ) I VESSEL 2 5TI,I LTNE I VOID RENdTIVITY 2 N(IPPLE8 fi'NiT I VI TT 3 SCRRi.I BTTl;T IvITT fTdtlifTe riiTiVITT-
6. rSECr H-NEF-SEP-5KI RT 9 LEVEL ( INCHES) D LEVEL ( INCI.IES} TFETI I TPCTJ -100. L 0. q. 6. TIHE ISECI V E L I I R sEh R SEt" ( R e v. L 2 L / 0 3 \\ Cffi"'"T) PERRY NUCLEAR POWER PLANT Generator Load Rejection W/O Bypass 3729 MWt Core Power 7 3. 6 2 F l o w F i g u r e 1 5 8. 3 - 2 ( S h e e t I o f 2 )
I VEssEL S R I S E ( P S I ) 2 STH LINE BEs RISE IPsI} VE FLOl'l (o) TY L0t4 [o) VE FLO}I [o) FL0I.I tPCT) q. TIHE 6. rSECf rSEC) ( R e v. L 2 1 / 0 3 ) PERRY NUCLEAR POWER PLANT Generator Load Rejection WlA Bypass 3729 MWt Core Power 7 3, 6 t F l o w F i g u r e 1 5 E. 3 - 2 ( S h e e t 2 o f 2 ) 2. TI},IE I VOID NEf;CTIVITT 2 OOPPLER RENCTIVITY
-SEP-sKIRT LEVEL ( INCHESI ( INCHESI ) [ 0. 15. TtHE [SEC) (ffi PERRY NU6LEAR POryER PLANT .N -a \\-)-(J Feedwater Controll-er Failure 3729 MWt Core Power 1058 Flow Figure l-58.3-3 (Sheet 1 of 2) R e v. 1 - Z f / 0 3 ) I LEVEL(I 2 H R
RISE (P5I I BISE IPSI I vE FLor.l tPcT) FLol.r (PCT) 1 0. 1 5. TI}4E ISEC) J} tr -1. (Jcr, lrJ E (Rev. Lz 1/!!-) rT()n ,V"ffi, PERRY NUCLEAR POWER PLANT LjA{J _v-Feedwater Controller Failure 3729 MWt Core Power f05t Flow F i g u r e 1 5 8. 3 - 3 ( S h e e t 2 o f 2 )
NEUTRON PERK FU 6 t00. lrJ cr ttr tr. o tt 50. (Jctr ldg 10. TIHE 15. (5ECl
- 10.
t5. TI}IE ISEC) ( R e v. t Z L / 0 3 ) l / A I I Cffi PERRY NUCLEAR POWER PLANT Feedwater Controller Failure 3'129 MWt Core Power 73.6t Fl-ow F i g u r e 1 5 E. 3 - 4 ( S h e e t L o f 2 ) T}
5 RI S E (P s I ) 5 RISE (PsII sUB IBTU/LBI VE FTOH (PCTI FLoH (PCT)
- 10.
15. TII,IE (SEC)
- 10.
15, TII,.IE (SECI ( R e v. 1 2 L / 0 3 ) ffiM PERRY NUCLEAR POWER PLANT Feedwater Controller Fai-lure 3129 MWt Core Power 73.6t FIow F i g u r e 1 5 E. 3 - 4 ( S h e e t 2 o f 2 \\ E LP L INE INE r vE55 2 5Tl.l 3 TURB Vl' F -l. L'ct lr,cc
5 VEssEL S q. TIr'rE rsEcr -sEP-5KIRT LEVEL(INCHES) VEL ( INCFIES) H (PCT) I (PCT) {.TIt'tE tSECt ( R e v. 1 2 l - l 0 3 ) t [ A l ffiM PERRY NUCLEAR POWER PLANT rli5/J Generator Load Rejection w/O Bypass 104.2t Power 105t Flow 250oF FWT Figure 158. 11-l" (Sheet L of 2l I 2 L ( I SEN 5EN LEVE ll B N R
U} F c-l G UJ TC T VESSEL 5 NISE (PSI ) 2 5TT,I LINE 5 R I S E I P S I ) SHFETY VE FLO,.I (o) VE FLOl.l (o) VE FLOi^l (o) FLoH (PCT) u.TIt,IE 6. rsEc) ( R e v. 1 2 1 / 0 3 ) l / ^\\ l Cffi"'M PERRY NUCLEAR POWER PLANT X..H Generator Load Rejection WlO Bypass LQA.2Z Power L05t Flow 250oF F'tfT F i g u r e 1 5 8. 1 1 - 1 ( S h e e t 2 o f 2 ) t VOID NTNTITIVITY 2 D0PFt.Ei] lrL fl[T I V ITY ? c.r nor.r F.$-ti.-'t t \\t I T Y 3 5CRRil Flt-fi;'l IVITY iiTtiT n'ri,i i i..'f i i, i=r'i-
I NEUTRON 2 PERK F CENTEN TEHP . F L U X FLCII.I 10, TII'IE 10. TI}IE 15. rSEC) 1 LEVEL ( I 2 H R S E N N H-REF-sEP-5KIBT D LEVEL ( INCHESI LEVEL(INCFIESI 15. rSECl ( R e v. L 2 1/ 03) n'On 1fffi PERRY NUCLEAR POWER PLANT - v - Feedwater Controller Failure 104,2* Power l-05t FIow 2500F FWT Figure 15E. LL-z (Sheet L of 2)
\\JESSEL ES RISE (P5I ) PBES RISE (P5I) ST}1 LINE Tllrmruruet vE FL0l.l IPCTI FLoH tPcTI I vo]mffidrtvtrr a/r,(inr LEn rl: li T I yl TY gmtrili{ivit+ F. F - 1. L) CE lrJ E
- lSECl (Rev. LZ t/03) ffi PERRY NUCLEAR POWER PLANT
-\\- Feedwater Controller Failure 704,22 Power 105t Fl-ow 2500F FWT F i g u r e 1 5 8. 1 1 - 2 ( S h e e t 2 o f 2 )
I NEUTBON 2 PERK F 5 VEsSEL 5 UX CENTER TEHP a 100. trJ CT (tr lt E' A 50. L)ctr lrJo-u.TII,IE {.TII4E ISEC) I LEVEL ( I H-REF-5EP-sK I RT t} LEVEL ( INCI-IEs) 2 H R N R S E LEVEL { INCHES) (Rev. t2 L /03 ) w/o PERRY NUGLEAR POWER PLANT Generator Load Rejection B l p a s s 1 0 4. 2 2 P o w e r 1 0 8. 7
- F L o w 3?OOF FWT F i g u r e 1 5 E. 1 1 - 3
( S h e e t 1 o f 2 )
5 BYPRSS V 6 TURB sTE S RI SE (PSI ) 5 R I S E I P S I ) F L 0 H ( o l VE FL0H (o) FLoH (PCT) u,TII4E 6. tSEC) T} L'clrJ E 2, TI},IE tSEC) ( R e v. T2 1/ 03 ) ribf,-\\ 6t'tb PERRY NUcLEAR PowER PI-ANT t_D(-r v Generator Load Rejection W/O BYPass 1'04,2* Power 1 0 8. ? t F I o w 3 7 0 o F F W T F i g u r e 1 5 E. 1 1 - 3 ( S h e e t 2 o f 2 ) I VEssEL P 2 STH LINE 3 SFFETY VOID NE OOPPLER
CENTER TEHP RT FLUX 6. rSEC) NEF-5EP-5KI BT LEVEL ( I NCHES) ( I NCHES) Low rPcT) I (PCT) -100. 0. u.TII,IE 6. (sEC) (Rev.. 12 1 / 0 3 )
- }b PERRY NUCLEAR POWER PLANT M-\\./-
Generator Load Rejection W/O BYPass 104-2? Power 110t Flow 320oF FWT F i g u r e 1 5 8. 1. 1 - 4 ( S h e e t 1 o f 2 ) L ( I 5EN SEN EVE R R
I VEssEL 2 5T}4 LINE o l LVE FL0tl (cl FLol.l rPcTl T I V I T Y R C T I V I T Y T I V I T T U} L'c! trJ E 2. TII,IE(5EC) ( R e v. L2 1/ 03) ffffi PERRY NUCLEAR POWER PLANT Generator Load Rejectlon W / O B y p a s s 1 0 4. 2 t P o w e r 110t Flow 320oF FWT F i g u r e 1 5 E. 1 1 - 4 ( S h e e t 2 o f 2 )
I NEUTNON 2 PERK FUE RVE 15. rSECl 15. rSEC ) (Rev. 1,2 1 / 0 3 ) TEHP RT FLUX Leveu t L!'tcHES) FMT-IPCT } t tPCT) -REF-5EP.5K I RT LEVEL ( I NCHES) UX CENTER A loo. tlJ FCT E tr-TD A 50. L) CC l! L 10. T II,IE 10. T I},1E r / > < \\ I d;$b PERRY NUCLEAR POWER PLANT r{,_y Feedwater Controller Fail-ure t04.22 Power L08t FJ-ow 3700r F.wr F i g u r e L 5 E. 1 L - 5 ( S h e e t I o f 2 ) V E L(I B sEN R sEN
5 RI S I (P s I ) NES RISE IPSI ) ( P 5 I } LB) VE FLOI"I IPCT) FL0l.'l IPCT) 10. TII4E 15. (SEC) vl F (-' CE lrJ E 10. TIHE (sEC) ( R e v. 1. 2 1 / 0 3 ) Ctr;N\\ PERRY NUCLEAR POWER PLANT -A 4 ( f v / l v Feedwater Controller Failure 1 Q 4. 2
- P o w e r 1 0 8 t F J o w 3700F rWT F i g u r e 1 5 8. 1 1 - 5 ( S h e e t 2 o f 2 )
VE55EL sTM LINE TURB I N v0l T I V I T Y T R C T I V ] T Y C T I V I T T
UX CENTER a 100. lrj ct ctr lr-a A so. L) G trJg 10. TIME t5. (sEc r -REF.5EP-SKI RT LEVELIINCHES) LEVEL I I N;HEs} to. 15. TII,IE ISECI ( R e v. L 2 r / 0 3 ) d6$5 PERRY NUcLEAR PowER PLANr \\J.l./ Feedwater Controller Failure ]-O4.2Z Power 1108 Flow 32OOF FWT F i g u r e 1 5 E. L l - 6 ( S h e e t 1 o f 2 ) L ( I SEN EVE n R L l.l
I VEssEL 2 sTH LINT T 5 R I S E ( P S I ) NEs NISE (PsI I R I S E ( P 5 I ) LB) LVE Fl"ol-l tPcTl FL0H tPcT) -tt'ol 10. TI}4E I (sECl {l' L)CT lrJ E, 1 0. 1 5. TIHE [SEC) ( R e v. 1 2 1 / 0 3 ) n'On ffi PERRY NUCLEAR POWER PLANT v Feedwater Controller Fai-lure L 0 4. 2 t P o w e r 1 1 0 t F l o w 32OOF FWT F i g u r e 1 5 E. 1 L - 6 ( S h e e t 2 o f 2 )
a 100. trJ cr cc ll E] A so. (J CE lrJg u. TII,IE ISEC)
- u.
6. TIHE tStCl (Rev. L2 1/q3) ^6^
- fib PERRY NUCLEAR POWER PLANT Generator Load Rejection W/O BYPass 104.2t Power 7 4. 8 t F I o w 3 7 0 o F F W T F i g u r e 1 5 8. 1 1 - ? ( S h e e t 1 o f 2 )
I LEVEL I INdH-REF-5EP-5K]RT 2I^I R SENSED LEVEL(INCHES) 3 N R SENSSD LEVEL(INCHES)
200. 100. 0. ES RISE (PSI) PRES RISE IPS1) LVE FLOW t>>) LVT70-1 VESSEL P 2 STM LINE 3 5RFETY V 4. 6. TIME (SEC) a 1 VOID RERC 2 DOPPLER F 3 SCRRMREf TIVITT ERCTIVITT CTIV1TT 2. 3. TIME ISEC) (Rev. 12 1/03) PERRY NUCLEAR POWER PLANT Generator Load Rejection W/O Bypass 104.2% Power 74.8% Flow 370°F FWT Figure 15E.11-7 (Sheet 2 of 2)
6 100. lrJ Cr Ctr Lo 2 .-il \\Il 6 v v ' cc trJg g. 6. TIME tSEC) NEUTRON LIX CENTEB E HERT PERK F TEHP RVE SURF FLUX LEVEL ( I NCH-BET-sEP-51(I RT LEVEL t I NCI-Ig5I Ft-Oi'l (PCT) I (PCT) -t 00.0.
- u.
6. TI}4E (SEC} ( R e v. 1 2 l / 0 3 ] r r n!a\\ '\\ ff'ffi PERRY NUCLEAR POWER PLANT Generator Load Rejection W/O Bypass L04.2* Power 73.7 t FLow 320oF FWT F i g u r e L 5 E. 1 L - 8 ( S h e e t 1 o f 2 l
I VESSEL 2 sTM LINE SRFETY s nl SE (PSi ) NEs R I SE IPSI I VE FL0i.l (ol VE FLOh (ol vE FL0l,,l. (o) FLOH (PCTI rl. TIt'lE (sECl J> L.'cf UJ (tr 2. TlttE I S E C ] ( R e v. L Z l / 0 3 ) l / > < \\ I (ffi-"6 PERRY NUCLEAR POWER PLANT N U \\jOU Generator Load Rejection W/O Blpass 1,04.22 Power '13.7\\ FIow 320oF FWT F i g u r e 1 5 E. 1 1 - B ( S h e e t 2 o f 2 ) VOID NERdT]VITY DOPPLER RENCTIVITT SCRRN NEH:TIVITY
t NEUTRON 2 PERK FUE RV CENTER TEI,1P RT FLUX H FL0l.r 10. TIHE 15. ISEC) H.REF-5EP-5K I RT O LEVEL (INCI.IE5) VEL ( INCI-IE5) 10. TII4E 15. rSEC) ( Rev. L2 1/ 03) ffi PERRY NUcLEAR PoWER PLANT X-ry Feedwater Controller Failure 1 0 4. 2 t P o w e r 7 4. 8 8 F l o w 370"F FWT F i g u r e 1 5 8. 1 1 - 9 ( S h e e t I o f 2 ) L I I 5EN t 2 LEVE HR NR
I VEssEL P 5 R I S E ( P S I ) 2 sTH LINE 3 TUBBINE 5 R I S E I P S I ) { F 5 I ) /LB) vE FL0l.r (PcT) FLoH IPCT) -25. L 0. t0. TII.IE 15. (sEC) ,y) F - 1. L)cl lrJcc 10. T I I,IErSEC) ( R e v. 7 2 L / 0 3 ) Cf,."*"}) PERRY NUCLEAR POWER PLANT X.X Feedwater Controller Failure I 0 4. 2
- P o w e r 7 4. 8 t F I o w 37OOF FWT F i g u r e 1 5 E. 1 1 - 9 ( S h e e t 2 o f 2 )
v0l
I NEUTH0N 2 PERK FUE 6 t00. lrJ Cf, Ctr LL o V. En L'ctr UJg
- 10.
15, TIt'lE tSEC) -5EP-5K I RT D LEVEL ( INCHES} LEVEL ( INCHES} 10. T I I,IErSEC) L(I 5EN ( R e v. t 2 I / 0 3 ) r /><\\ l ff"',b PERRY NUCLEAR PoWER PLANT r.)cry Feedwater Controller Failure l A 4. 2 Z P o w e r 7 3. 7 t F l o w 32OOF FWT F i g u r e L 5 E. 1 1 - 1 0 ( S h e e t L o f 2 )
,yl' CJ CE u.J 0c I VESSEL 5 NISE (PsI ) 2 5TI.,I LINE 5 R I S E ( P 5 I I TUR 5 R I S E ( P S ] } SUB (BTU/LB) VE FLOI,I (PCT I FLor.r I PcT ) 10. T I I.4E 15. ISEC) (sECl (Rev. 12 1 / 0 3 ) ffi PERRY NUCLEAR POWER PLANT \\JO{J Feedwater Controller FaiLure L 0 4, 2 2 P o w e r 7 3. 7 t F l o w 32OOF FWT F i g u r e 1 5 8. 1 1 - 1 0 ( S h e e t 2 o f 2 ) 10. T I I,,IE
l{. = Total Core FI ow t{; - Actlve LooP Flow tli = Inactive LooP Flow ( R e v. t 2 t / 03) tr'ffi PERRY NUCLEAR POWER PLANT t \\ > < /, - v - fllustratj-on of Single Recireulation LooP Operation Fl-ows F i g r u r e 1 5 F. 2 - 1
.tt vl CL oL UI .A qJ L CL o EJ a 4lr'o CL I 230 12?0 l2r 0 I ?00 I190 I 180 I170 I160 Ils0 without bypass wi th bypass 60 70 80 90 Initla'l Power Level (; NBR) 100 'll0 ( R e v, L 2 1 / 0 3 ) n'art tr-D PERRY NUCLEAR POWER PLANT w Peak Dome Pressure Versus Initial Power Level, Turbine Trip at EOEC F i g u r e 1 5 f. 3 - 1
a t00. lr, CE cc t! t A 50. IJCtr lrJ o-il P 5 F-SEP-sI(I RT I T I 0 N ( o l FI.ICF.IIFX DEI.IR },I/ HI.IL TRIPS ( R e v, 1 2 l / 0 3 ) F PERRY NUCLEAR POWER PLANT eedwater ControlLer Failure Maximum Demand Single Loop Operations a F i g u r e 1 5 F. 3 - 2 ( S h e e t 1 o f 2 )
RISE (P5I I RISE IPSI) (P5I } c ( o l (PCTI 0H2 FL0l.l I5. (sECl G F. F - I. L' CI trJ G t2 55EL P H LINE RBI NE VE ST TU I vCIlD BEndIIyIIY 2 OOPPLER -H7- -\\t-:L { bPi.F'R J v t t v \\*# F PERRY NUCLEAR POWER PLANT eedwater ControLler Failure Maximum Demand Single LooP OPerations F i g u r e 1 5 F. 3 - 2 ( S h e e t 2 o f 2 ) R e v. 03
BON TEI.lP E 100. lrj crItr l.t. E F 2 L t I u J\\,' E, l4J 5 u. TI}IE 6. rsEcl I LEVEL(I 2F Cv t P H-REF-sEP-5KIBT ITI0N Iol 100. 0. TIHE ISECI 1f"ffi PERRY NUcLEAR POWER PLANT v Generator Load Rejection, w/O Blpass Single LooP Operation F i g r u r e 1 5 F. 3 - 3 ( S h e e t 1 o f 2 ) ( R e v. 1 2 L / 0 3 )
I VESSEL RISE (PsI I 2 ST}I LINE RI SE IPSI I ( o l o l VE FL0l'l (ol FLfH (PCTI tl. TII'IE 6. (sECr t-(J G t^J Itr 2. TII,IE rsEcr v0l0 RE DOPPLER TIVITY CTIVITY IVITY ( R e v. L Z L / 0 3 ) CqA"il\\ PERRY NUCLEAR POWER PLANT L ^ / Generator Load Rejectiont W /O BlPass Single Loop Operation Figure 15F.3-3 (Sheet 2 of 2)}}